Invitation with Preliminary Programme

Transcription

Invitation with Preliminary Programme
The PATRAM Conference Series
First International Symposium on the
Packaging and Transportation
of Radioactive Materials
Albuquerque, N. M., USA (January 12 - 15, 1965)
Second International Symposium
Gatlinburg, Ten., USA (Oktober 14 - 18, 1968)
Third International Symposium
Richland, Wash., USA (August 16 - 20, 1971)
Fourth International Symposium
Miami Beach, Fl., USA (September 22 - 27, 1974)
Fifth International Symposium
Las Vegas, Nev., USA (May 7 - 12, 1978)
6th PATRAM '80
Berlin, Germany (November 10 - 14, 1980)
7th PATRAM '83
New Orleans, Lou., USA (May 15 - 20, 1983)
8th PATRAM '86
Davos, Switzerland (June 16 -20, 1986)
9th PATRAM '89
Washington DC, USA (June 11 - 16, 1989)
10th PATRAM '92
Yokohama City, Japan (September 13 - 18, 1992)
11th PATRAM '95
Las Vegas, Nev., USA (December 3 - 8, 1995)
12th PATRAM '98
Paris, France (May 10 - 15, 1998)
13th PATRAM 2001
Chicago, Il., USA (September 3 - 7, 2001)
14th PATRAM 2004
Berlin, Germany (September 20 - 24, 2004)
14th INTERNATIONAL SYMPOSIUM ON THE PACKAGING
AND TRANSPORTATION OF RADIOACTIVE MATERIALS
ESTREL Convention Center, Berlin, Germany
September 20-24, 2004
GENERAL INFORMATION/ PRELIMINARY PROGRAMME
Message from the Chairman
The German Federal Institute for Materials Research and Testing (BAM) will host the 14th
International Symposium on the Packaging and Transportation of Radioactive Materials
(PATRAM 2004) during September 20-24, 2004 in Berlin, Germany.
PATRAM 2004 will be held under the auspices of the German Federal Minister for Transport,
Building and Housing, Dr. Manfred Stolpe.
In cooperation with the International Atomic Energy Agency (IAEA) and the US Institute for
Nuclear Materials Management (INMM) the symposium will be performed in continuity to former PATRAM meetings.
Every three years this symposium gives the representatives of industry, administrations and
research institutes worldwide the opportunity to meet and exchange views and information on
all aspects of the safe packaging, transport and storage of radioactive materials.
In the period since the last PATRAM conference the revised IAEA Regulations for The Safe
Transport of Radioactive Materials, TS-R-1, have been implemented in the international and
national regulations. The 2004 symposium will form a forum to reflect experiences with the
implementation and look forward to proposed improvements.
As a whole the symposium shall underline the sound technical and scientific basis for the safe
packaging, transportation and storage of radioactive materials, including necessary security
aspects and giving support in the discussion of public concern. I am proud to announce that
about 290 submitted papers are incorporated in this preliminary programme.
After 1980 PATRAM will again be held in Berlin, now really the capital of the re-unified Germany.
I enjoy inviting you to Berlin for PATRAM 2004!
Prof. Dr. Bernd Schulz-Forberg
Conference Chairman
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Bundesanstalt für Materialforschung und -prüfung BAM
International Atomic Agency IAEA
Institute for Nuclear Materials Management INMM
What is PATRAM?
PATRAM, the International Symposium on the Packaging and Transportation of Radioactive
Materials, is a series of symposia that brings together worldwide experts from government,
industry and research organizations to exchange information on all aspects of packaging and
transportation of radioactive materials. The Symposium has become the premier forum in the
world devoted entirely to this subject.
PATRAM takes place every three years alternately in the United States and a non-U.S. location.
PATRAM 2004 is hosted by Bundesanstalt für Materialforschung und –prüfung (BAM) in cooperation with the International Atomic Energy Agency (IAEA) and the Institute of Nuclear
Materials Management (INMM).
Topics to be discussed comprise:
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Packaging and Components Technology / Engineering
National and International Regulations and their applications and implications
Transport Systems
Transport Operational Experience
Public Perception and Institutional Issues
Tracking of Conveyances and Emergency Response
Radiation Exposure and Environmental Impact
Fuel Cycle Integration
On Site Handling & Transport Requirements and Practices
Radioactive Waste packaging in decommissioning and disposal activities
Security concerns in radioactive materials transportation and storage
Containment for Interim storage of spent fuel and high level waste
Safety assessment methodologies
Who should attend?
· Packaging and Transportation Professionals
· Academic Institutions
· Regulatory Officials
· Hazardous Materials Response Units
· Government and Public Officials
· Radioactive Pharmaceutical Personnel
· Government Contractors
· Carriers (rail, highway, air, and water)
· National Laboratories
Utilities
· Packaging Industry Officials
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Preliminary Programme Structure
Sunday, September 19, 2004
02.00 p.m. – 10.00 p.m.
06.00 p.m. – 08.00 p.m.
Exhibitor Set-up
Registration/ Counter open
Monday, September 20, 2004
07.45 a.m. – 06.00 p.m.
07.45 a.m. – 08.45 a.m.
09.00 a.m. – noon
Speakers Breakfast
'Welcome and Opening
Plenary Session
Exhibition
Concurrent Sessions
Opening Reception
Exhibition area
10.00 a.m. – 08.00 p.m.
01.30 p.m. – 05.10 p.m.
06.00 p.m. – 08.00 p.m.
Tuesday, September 21, 2004
07.00
07.15
08.30
09.00
09.10
01:30
a.m.
a.m.
a.m.
a.m.
a.m.
p.m.
–
–
–
–
–
–
06.00
08.15
09.00
06.00
12.30
06.00
p.m.
a.m.
a.m.
p.m.
p.m.
p.m.
Speakers Breakfast
Plenary Session
Exhibition
Concurrent Sessions
Technical Tour
Wednesday, September 22, 2004 07.00
07.15
.
08.30
09.00
09.10
03.30
03.30
a.m. – 06.00 p.m.
a.m. – 08.15 a.m.
a.m.
a.m.
a.m.
p.m.
p.m.
–
–
–
–
–
09.00
06.00
03.10
05.00
06.00
a.m.
p.m.
p.m.
p.m.
p.m.
Speakers Breakfast/
Poster Session Breakfast
Plenary Session
Exhibition
Concurrent Sessions
Panel Discussion
Special Session - Poster
Thursday, September 23, 2004
07.00
07.15
08.30
09.00
09.10
07.00
a.m.
a.m.
a.m.
a.m.
a.m.
p.m.
–
–
–
–
–
–
06.00
08.15
09.00
06.00
05.10
10.00
p.m.
a.m.
a.m.
p.m.
p.m.
p.m.
Speakers Breakfast
Plenary Session
Exhibition
Concurrent Sessions
Banquet
Friday, September 24, 2004
07.00
07.15
08.30
09.00
09.10
01.30
a.m.
a.m.
a.m.
a.m.
a.m.
p.m.
–
–
–
–
–
–
12.30
08.15
09.00
06.00
12.10
07.00
p.m.
a.m.
a.m.
p.m.
p.m.
p.m.
Speakers Breakfast
Plenary Session
Exhibition
Concurrent Sessions
Technical Tour
The information provided here is preliminary. There may be changes in presentation and locations. Please check www.patram2004.com for updated information.
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Speakers/ Session Chairs Breakfast
Breakfasts and briefings are scheduled for each morning of the conference, times see above.
On the day of your presentation, please attend this breakfast/ briefing to hear last-minute communications on changes, introductions, etc. between speakers and chairs. You should notify the
PATRAM 2004 Conference Agency (phone: ++49/40/527 48 28 – fax: ++49/ 40/ 507 988 34) if
you cannot attend. Only the speaker respectively one author per presentation should attend.
The same goes for the poster presentation: only one author per poster should attend the poster
breakfast/ briefing.
Full registration
Participation in PATRAM 2004 is limited to registered attendees only. A full registration includes:
· Admission to all sessions (Monday – Friday)
· Access to all exhibits
· Entry to view poster sessions
· Opening Reception*
· Daily coffee and refreshment breaks
· Banquet*
· A compact disc of the proceedings*
· Please note: these are not included with one-day registration.
Registration Fees
(all fees are excl. VAT)
On or before August 9, 2004
Full registration
€ 690,One-Day registration* € 240,Accompanying Person € 110,-
After August 9, 2004 and on site
Full registration
€ 790,One-Day registration* € 240,Accompanying Person € 110,-
* One-Day registration fee includes admission to all technical sessions, refreshment breaks and
exhibits scheduled for the day purchased (banquet and opening reception are not included).
All meeting participants including speakers, session chairpersons and committee members
must pay the appropriate registration fee.
Accompanying Person’s Programme
Guests of PATRAM 2004 registered attendees are invited to participate in the Accompanying
Person’s Programme. Each morning accompanying persons are invited to meet in the
Accompanying Person’s Hospitality Suite at 08.30 a.m. to socialize and obtain information on
formally arranged or “on your own” activities. Registered accompanying persons will receive a
name badge for admittance to the Accompanying Person’s Hospitality Suite, the Opening
Reception on Monday evening and the Banquet on Thursday evening.
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Please register your accompanying persons prior to the conference using the PATRAM 2004
registration form. This will ease badge printing and facilitate the registration process at the registration desk/ counter.
Important Registration Information
Registration
· To register please completely fill-in the registration form attached to this brochure and return
it to the PATRAM 2004 Conference Agency either by telefax, mail or Email.
· PATRAM 2004 Conference Agency
c/o Kontec – Gesellschaft für technische Kommunikation
Tarpenring 6 · D-22419 Hamburg · Germany
Phone: ++49/40/ 527 48 28 · Fax: ++49/40/ 507 988 34
Email: [email protected]
· Please do not send duplicate copies of your registration, if you register via fax, mail or Email,
it is not necessary to follow up with a second registration using the same of an alternate delivery method.
Confirmation of registration
· A list of confirmed registrants will be posted every 2 to 3 weeks on www.patram2004.com.
Please check the Web site to verify your organization.
· Independent of the payment method (bank transfer or credit card), each registrant will receive
an invoice by mail. Please review the payment method instructions at the bottom of the
invoice. Please avoid double payment, if you stated your credit card no. on your registration
form, it is not necessary to effect a bank transfer.
· The invoice is at the same time the written registration confirmation for each registrant.
· All registered attendees may pick up their registration package at the PATRAM 2004
Registration Desk/ Counter during the following times:
Sunday, September 19, 2004
Monday, September 20, 2004
Tuesday, September 21, 2004
Wednesday, September 22, 2004
06.00
07.45
07.00
07.00
07.00
07.00
p.m.
a.m.
a.m.
a.m.
a.m.
a.m.
–
–
–
–
–
–
08.00
06.00
06.00
06.00
06.00
12.30
p.m.
p.m.
p.m.
p.m.
p.m.
p.m.
Payment
· Payment of fees to be made in EURO funds (€) either by bank transfer or by credit card
(VISA, EUROCARD/ MASTERCARD or AMERICAN EXPRESS only).
· Payment of all fees (except for technical tours) is to be made in time prior to the conference
to allow access to the conference.
Cancellation of Registration
· Notification of cancellation must be done in writing.
· Registration change for an alternate participant must be done in writing until 2 weeks prior to
the conference at the latest and is free of charge.
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· For cancellation until/on August 20, 2004, a handling fee of € 75,- plus VAT will be retained.
No refund can be made after August 20, 2004.
Conference location
ESTREL Convention Center, Berlin ? Sonnenallee 225 ? D-12057 Berlin ? Germany
Hotel accommodations/ Conference hotel
ESTREL Residence & Congress Hotel, Berlin ? Sonnenallee 225 ? D-12057 Berlin ? Germany
Phone: ++49/ 30/ 6831 0 ? Fax: ++49/ 30/ 6831 2345
Web site: http://www.estrel.com
Prices: (hotel prices incl. VAT)
Single standard room:
Double standard room:
(Breakfast buffet € 14,50 per person)
€ 115,- per night excl. breakfast
€ 126,50 per night excl. breakfast
The ESTREL Berlin is Europe’s largest Convention, Entertainment & Hotel Complex. The
ESTREL Hotel with its 1125 rooms and 70 suites is not only Germany’s largest Hotel; it also
offers a unique experience which combines living, congress and entertainment. The ESTREL
offers a glass-covered Atrium with 5 restaurants, Mediterranean atmosphere and a traditional
German beer garden. The ESTREL Hotel is in the south not far away from the Berlin City and
the 3 major airports. The Las Vegas Live Show “Stars in Concert” takes places in the ESTREL
Festival Center since September 1997. With over 1.2 mio visitors it is one of the most successful shows in Berlin.
How to find
Airport Tegel: Highway 100/102,
www.bvg.de
Descent Buschkrugallee
ca. 30 Min.
For public traffic information see:
Airport Tempelhof: Highway 102,
Descent Buschkrugallee
ca. 10 Min.
For tourist information see: www. btm.de
Airport Schönefeld: Descent B96a to
Baumschulenstraße, then Sonnenallee
ca. 20 Min.
From station Zoologischer Garten via S3, S5, S7, S75 or S9 to Ostkreuz, switch to S41 until
stop Sonnenallee
From Ostbahnhof via S5, S75 or S9 to Ostkreuz, switch to S41 until stop Sonnenallee
S-Train S 41, 42 (Stop Sonnenallee)
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or Bus Nr. 241 (Stop Ziegrastrasse)
Web Site
www.patram2004.com
Language
PATRAM 2004 will be conducted in English
PATRAM 2004 Proceedings
Papers accepted for oral and poster presentations will be published in the Proceedings of
PATRAM 2004 on compact disc in PDF format. PATRAM 2004 does not charge for publishing
presented papers that are less than eight full, single-spaced, single-column pages (including
charts and photos). Papers longer than eight pages will be assessed a fee of € 50,- per page
for each page over eight.
The Proceedings will be mailed by March 1, 2005. One-Day registration does not include a copy
of the Proceedings; however, the disc will be available for separate purchase. For additional
information, please visit the PATRAM 2004 Web site or contact the PATRAM 2004 Conference
Agency (phone: ++49/ 40/ 527 48 28 · fax: ++49/ 40/ 507 988 34 · Email:
[email protected]).
Attention Exhibitors, Sponsors and Advertisers
PATRAM 2004 invites you to be an exhibitor, sponsor or advertiser. All exhibitors, sponsors and
advertisers will be acknowledged in the PATRAM 2004 Final Programme.
Advertising is possible in various media (Final Programme brochure, post-signing at the symposium, compact disc cover, Web site…). Please contact PATRAM 2004 Conference Agency
(phone: ++49/ 40/ 527 48 28 · fax: ++49/ 40/ 507 988 34 · Email: [email protected]).
Separate detailed information on the technical exhibition are available on
www.patram2004.com/exhibition. In case of interest please also contact PATRAM 2004
Conference Agency (phone: ++49/ 40/ 527 48 28 · fax: ++49/ 40/ 507 988 34 · Email:
[email protected]).
Increase your company’s visibility in the industry by participating in this international
exchange.
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SESSIONS
Monday, September 20, 20 4
9:00 a.m. – 12:00 p.m.
1.0 Welcome and Opening Plenaries
Manfred Stolpe, German Federal Minister of Transport, Building and Housing
Bernd Schulz-Forberg, BAM, Conference Chairman
Michael E. Wangler, International Atomic Energy Agency (IAEA)
US Department of Energy
Invited Speakers:
International Maritime Organization
Christian Waeterloos, European Commission, Directorate for Nuclear Safety and Safeguards
Lorne Green, World Nuclear Transport Institute
Ralf Güldner, Framatome ANP/Kerntechnische Gesellschaft
12:00 p. m. – 1:30 p. m. Lunch Break
1:30 p. m. – 3:10 p. m.
1.1 Institutional - 1
Public Perception of the Transport of Radioactive Materials
Ramesh C. Malik, Supdt. (Training & Public Awareness) HWPK; B. Ramamirtham, Head
(Health Physics Group) NPCIL
The Need for a Public Information Program to Promote Understanding of the Validity of
the Safety of IAEA Transport Regulations for Shipment of Radioactive Material
Minoru Kubo, Japan Nuclear Cycle Development Institute
Communications Issues for International Radioactive Materials Transport, post 9/11.
A. A . Brown, International Transport, BNFL; H.-J. Neau, Cogema Logistics; M. Nawano,
Transport Headquarters, overseas Reprocessing Committee
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Transparency and Dialogue: The Keys of Radioactive Material Transportation
Henry-Jacques Neau, Cogema Logistics
Further Activities of Safety Culture toward Nuclear Transportation Industry
Yuzo Machida, Hideki Takatsuki, Nuclear Safety Network
1.2 Spent Fuel Package Design - 1
The Use of the CONSTOR Cask Concept for Light Water Reactor Fuel
Thomas Funke, Rudolf Diersch, Gesellschaft für Nuklear-Behälter (GNB)
Development of Transport and Storage Cask for High Burn Up Spent Nuclear Fuel of
German Nuclear Plant
Shuhei Kuri, Hiroki Tamaki, Suguru Hode, Mitsubishi Heavy Industries, Ltd.
NAC’s Advanced, Threat Limiting All-Purpose Storage (ATLAS) System: New
Generation Multipurpose Spent Fuel Storage for Global Application
Charles W. Pennington, NAC International
Development of New PWR Type Transport Casks
Yu Nakamura, T. Takakura, Engineering Department Nuclear Fuel Transport Co.; K.
Kawakami, T. Matsumoto, OCL
New Generation of CASTOR Casks for High Enriched, High Burn-Up Fuel from German
NPP
Robert Gartz, Bernhard Kühne, Rudolf Diersch, Gesellschaft für Nuklear-Behälter (GNB)
1.3 Transport Experience General
Transport of Radioactive Material for Nuclear Applications in India: A Profile
Krishna Upadhyay, S. P. Agarwal, Atomic Energy Regulatory Board
The French Nuclear Safety Authority’s Experience with Radioactive Transport
Inspection
Emmanuel Jacob, Direction Générale de la Sureté Nucléaire
30 Years of Experience in Safe Transportation of Nuclear Materials
Kohji Kaneko, Nuclear Fuel Transport Co., Ltd.
Five Steps to Delivering Safe, Secure & Reliable Rail Solutions for the Nuclear Industry.
C. Connolly, BNFL
Assessment of Radiation Dose to the Radiation Workers
Mohamad Bagher Tavakoli, Isfahan University of Medical Sciences; M. R. Divband, M.
Ghiasinejad, S. Borhanazad, Iran Atomic Energy Agency
Transportation of Intermediate-level Radioactive Liquid Waste and Spent Fuel
Jinying Li, China Institute of Atomic Energy
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1.4 Structural Analysis Justification
Comparison of Analytical and Physical Testing Results for the DPP-2 Shipping
Package
Matthew Feldman, K. D. Handy, P. T. Singley, R. D. Michelhaugh, M. B. Hawk, Larry B.
Shappert, Oak Ridge National Laboratory
Forty Five Years of Package Testing at ORNL – A Look Back
Larry B. Shappert, Scott B. Ludwig, Oak Ridge National Laboratory
Validation of an Impact Limiter Crush Prediction Model with Test Data:
The Case of the HI-STAR 100 Package
K.P. Singh, A.I. Soler, C. Bullard, Holtec International
CONSTOR Full Scale Prototype Drop Test and Measuring Program
Sabine König, Gesellschaft für Nuklear-Behälter (GNB); Thomas Quercetti, Bundesanstalt für
Materialforschung und –prüfung (BAM)
CONSTOR V/TC Drop Tests - Pre Tests Analysis by Finite Element Method
Sabine König, Karl Klein, Walter Völzer, Gesellschaft für Nuklear-Behälter (GNB); Chi-Fung
Tso, Sarah Owen, Chris Monk, Arup
3:10 p.m. – 3:30 p.m. Coffee break
3:30 p.m. – 5:10 p.m.
1.5 Institutional - 2
Performance of the IAEA Transport Regulations in Controlling Doses and Risks from a
Large-Scale Radioactive Waste Transport System
David Hutchinson, UK Nirex Ltd.; Richard Miles, RM Consultants Ltd.; I. F. White IFWtech Ltd.
Denial of Shipments - Myth or Reality
Marc-Andre Charette, P. Eng, MDS Nordion
INES scale : French Application to Radioactive Material Transport
Séverine Sowinski, Sophie Strawa, DGSNR
Challenges and Issues with Building a Potential Railroad to Yucca Mountain
Robin L. Sweeney, US Department of Energy
Fostering Member State Implementation of the IAEA\’s Transport Regulations
M.T.M. Brittinger, Michael W. Wangler, International Atomic Energy Agency
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1.6 Spent Fuel Package Design - 2
Developing New Transportable Storage Casks for Interim Dry Storage
Katsuyuki Hayashi, Kazuo Iwasa, Kenji Araki, Ryoji Asano, Hitachi Zosen Corp.
A Complete NUHOMS® Solution for Storage and Transport of High Burnup Spent Fuel
Jayant Bondre, Transnuclear, Inc. (AREVA GROUP)
Design of Double Containment Canister Cask Storage System
T. Oohama, Plant Engineering Group, Nuclear Poer Division, The Kansai Electric Power Co.
Inc.; K. Kuriyama, Engineering Department, Nuclear Fuel Transport Co., Ltd; K. Kawakami,
Design Devision, OCL Corporation; Tsutomu Matsumoto, Design Devision, OCL Corporation
Osaka Branch Office
Transporting Existing VSC-24 Canisters Using a Risk-Based Licensing Approach
Ram Srinivasan, James E. Hopf, BNFL Fuel Solutions
Conception of Transport Cask with Advanced Safety, Aimed at Transportation and
Storage of Spent Nuclear Fuel of Power Reactors, which meets the Requirements of
IAEA in Terms of Safety and Increased Stability during Beyond-Design-Basis Accidents
and Acts of Terrorism
R. I. Il´kaev, Vitaly Z. Matveev, A. I. Morenko, V. I. Shapovalov, RFNC-VNIIEF; A. G.
Semenov, V. M. Sergeyov, V. K. Orlov, All-Russian Research Institute of Inorganic Materials
named after Bochvar A. A.; V. V. Shatalov, V. T. Gotovchikov, V. A. Seredenko, All-Russian
Research Institute of Applied Chemistry; M. Jonathan Haire, Charles W. Forsberg, Oak Ridge
National Laboratory
1.7 Radiation Protection
A Survey of the Transport of Radioactive Materials by Air to from and within the UK
Stuart Hughes, S. J. Watson, National Radiological Protection Board
Lessons Learned From the Studsvik Ir-192 Transport Incident
Richard Boyle, US Department of Transportation
Experience of Air Transport of Nuclear Fuel Material in Japan
Tadahiko Yamashita, Daisuke Toguri, Transnuclear, Ltd; Masashi Kawasaki, Japan Nuclear
Cycle Development Institute
BNFL’s Experience in Preparing and Implementing Radiation Protection Programmes
for the Control of Exposure to Workers Involved with the International Transport of
Nuclear Cargoes
D. Billing, BNFL
Air Shipment of Radioactive Materials in Depleted Uranium Shielded Packaging
Vladimir Adaev, E. S. Kalevich, Federal State Unitary Enterprise “State Scintific Centre of
Russia Research Institute of Atomic Reactors”; Yu. A. Metelkin, V. K. Orlov, Federal State
Unitary Enterprise Academician Bochvar, All-Russian Research Institute of Inorganic Materials
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1.8
Structural Response Assessment by Tests
Certification Testing at Low Temperatures
Philip W. Noss, Packaging Technology Inc.; Douglas J. Ammerman, Sandia National
Laboratories
Recent Package Testing Successes at Oak Ridge National Laboratory
Scott B. Ludwig, P. T. Singley, R. D. Michelhough, M. B. Hawk, Larry B. Shappert, Oak Ridge
National Laboratory
Certification Testing of the MOX Fresh Fuel Package (MFFP)
Joseph C. Nichols III, Fred Yapuncich, Packaging Technology Inc.
Test Program of the Drop Tests with Full Scale and 1/2.5 Scale Models of Spent Nuclear
Fuel Transport and Storage Cask for German Nuclear Plants
Shuhei Kuri, Toshihiro Matsuoka, Junichi Kishimoto, Daiichi Ishiko, Yuichi Saito, Tadashi
Kimura, Mitsubishi Heavy Industries, Ltd.
Qualification Test for a Type B (U) Package
Gheorghe Vieru, Inst. For Nuclear Research
6:00 p.m.- 8:00 p.m. Opening Reception
Exhibition Area
Tuesday September 21, 2004
8:30 a. m. – 9:00 a. m.
2.0
Plenary
Japanese Perspectives and Research on Packaging, Transport and Storage of Spent Fuel
Toshiari Saegusa, C. Ito, H. Yamakawa, K. Shirai, CRIEPI
9:10 a. m. – 10:30 a. m.
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2.1 Package Operations and Maintenance - 1
Aging Management Assessment of a Type B Transportation Package
Gord Sullivan, Ontario Power Generation
Operational and Maintenance Experience of “Wet” Flask Transports.
D. S. McWilliam, BNFL
Design of Casks: Incorporating Operational Feedback from Maintenance
Michel Hartenstein, Laurent Michel, Cogema Logistics (Areva Group)
NTL11 Spent Fuel Flask – Meeting the Challenge of Regulatory and Technological
Change
A. Cory, BNFL
2.2 Security - 1
Security of Radioactive Material During Transport
A. Hagemann, P. Legoux, R. Pope, Michael Wangler, IAEA
Regional, National and International Security Requirements for the Transport of
Nuclear Cargoes by sea.
Capt. P.Booker, BNFL
Truck Shipment Risks for Hazardous Materials: A New Paradigm Incorporating Safety
and Security
Art Greenberg, John Allen, Mark Lepofsky, Tom McSweeney, Battelle Memorial Institute;
Mark Abkowitz, Department of Civil Engineering, Vanderbilt University.
Development of International Standards for RAM Shipment Security
Robert E. Luna, Consultant
2.3 Fracture Mechanics - 1
Draft ASME Code Case on Ductile Cast Iron for Transport Packaging
Toshiari Saegusa, T. Arai, CRIEPI; M. Hirose, NFT; T. Kobayashi, Nippon Chuzo; Y. Tezuka,
MMC; N. Urabe, KKS; Roland Hüggenberg (GNB)
Fracture Mechanics Code Case for American Society of Mechanical Engineers
NUPACK Rules
Paul McConnell, Ken Sorenson, Sandia National Laboratories; Robert Nickell, Applied
Science & Technology; Toshiari Saegusa, Central Research Institute of Electric Power
Industry
The Application of Fracture Mechanics to the Safety Assessment of Transport Casks
for Radioactive Materials
Uwe Zencker, Karsten Müller, Bernhard Droste, Roland Rödel, Holger Völzke, Bundesanstalt
für Materialforschung und –prüfung (BAM)
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Demonstration of Freedom from Brittle Fracture - Validation of the Master Curve
Methodology for Deriving Material Fracture Toughness
Frank Norton, BNFL; Henryk Pisarski, TWI
2.4 Package Response to Fires - 1
Thermal Modelling of the SAFESHIELD 2999A Package
Chris Fry, Serco Assurance; Bob Vaughan
Lessons Learned from the Fire Test of Westinghouse’s New Type AF Package, the
Traveller: (Nothing like the Real Thing)
John Malloy, VA; Brian Hempy, Russ Utlak; Norman Kent, Westinghouse Electric Company
Numerical Study of the Thermal Behaviour of two Types of Packages Exposed to Long
Duration Fires
Olivier Doaré, F. Armingaud, G. Sert, Institut de Radioprotection et de Sureté Nucléaire; H.
Issard, Cogema Logistics
Three-Dimensional Simulations of a Generic Truck Cask in Regulatory Format Fires
Using the Container Analysis Fire Environment (CAFE-3D) Computer Code
Narendra Are, Miles Greiner, University of Nevada, Reno; Ahti Suo-Anttila, Alion Science and
Technology, Inc.
10:30 a.m. – 10:50 a. m. Coffee break
10:50 a. m. – 12:30 p. m.
2.5 Package Operations and Maintenance - 2
Two Decades of Experience with more than 750 CASTOR and CONSTOR Transport and
Storage Casks
Bernhard Kühne, Wolfgang Sowa, Gesellschaft für Nuklear-Behälter (GNB)
GNB Experience of CASTOR Cask Loadings for Storage and Transport of Spent Fuel
Assemblies
Marco Wilmsmeier, Gesellschaft für Nuklear-Behälter (GNB)
The First Commercial Spent Fuel Shipment in China
Xiaoqing Li; Norman Meinert, NAC International
The BG18, a B(U)F Type Package Used for the Transport of Irradiated Fuel Rods.
Return of Experience.
Jürgen Sperlich, Herman Sannen, Transnubel
Authorised Radioactive Contents of Packages: How to Maximise Simultaneously Safety
and Flexibility?
Pierre Malesys, Cogema Logistics (Areva Group); Greg Field, Packaging Technology, Inc.
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2.6
Security - 2
Initiation of Depleted Uranium Oxide and Spent Fuel Testing for the Spent Fuel
Sabotage Aerosol Ratio Program
Martin A. Molecke, M. W. Gregson, Ken B. Sorenson, Sandia National Lab.; H. Tsai, M. C.
Billione, Argonne National Laboratory; W. Koch, O. Nolte, Fraunhofer Institut für Toxikologie
und Experimentelle Medizin; G. Pretzsch, F. Lange, Gesellschaft für Anlagen- und
Reaktorsicherheit; B. Autrusson, O. Loiseau, Institut de Radioprotection et de Surete
Nucleaire; N. Slater Thompson, R. S. Hibbis, USDOE; F. I. Young, U. S. Nuclear Regulatory
Commission
Response of Spent Fuel Transportation Casks to Explosive Loadings
Douglas Ammerman, Marlin E. Kipp, Jeffrey A. Smith, Sandia National Laboratories
Safety and Security in Transportation of Radioactive Material - The Perception of Risk
Ann-Margret Ericsson, Clifford Järnry, AMC Konsult AB
Loads imposed on Dual Purpose Casks in German On-Site-Storage Facilities for Long
Term Intermediate Storage of Spent Nuclear Fuel
N. Wetzel, O. Rabe, TÜV Hannover/Sachsen-Anhalt e.V.
(Topic of the paper belongs to session 5.3)
Estimation of Terrorist Attack Resistibility of Dual-Purpose Cask TP-117 with DU
(Depleted Uranium) Gamma Shield
O. G. Alekseev, Vitaly Z. Matveev, A. I. Morenko, R. I. Il´kaev, V. I. Shapovalov, RFNC-VNIIEF
2.7 Fracture Mechanics - 2
Candidate Materials to Prevent Brittle Fracture
Roland Vincent, Yves Chanzy, Cogema Logistics (Areva Group)
Dynamic Fracture Toughness Data for CASTOR Casks
Hans-Peter Winkler, Gesellschaft für Nuklear-Behälter (GBN); P. Trubitz, G. Pusch; E. P.
Warnke; K. Beute; V. Novotny
Design Concept for Maximized Use of Recycled Scrap in the Production of Storage
Packages
Dieter Bounin, W. Kleinkröger, Siempelkamp Giesserei; D. Schreiber, Gesellschaft für
Nuklear-Service (GNS)
Development of Assessment Methods for Transport and Storage Containers With
Higher Content of Metallic Recycling Material
Uwe Zencker, Linan Qiao, Bernhard Droste, Bundesanstalt für Materialforschung und –prüfung (BAM)
Radiation Effects on the Mechanical Properties and Long Term Aging of Spent Fuel
Storage Containers.
Laurent Brissonneau, Commissariat à l’Energie Atomique (CEA Valrhô); Alain Barbu, JeanLous Bocquet, Commissariat à l’Energie Atomique (CEA Saclay)
16
2.8 Package Response to Fires - 2
Calibration of the CAFE-3D Fire Code with Controlled Indoor Fire Data
Carlos Lopez, Sandia National Laboratories; Ahti Suo-Anttila, Alion Science and Technology;
Jorman A. Koski, Consultant to Sandia National Laboratories
FDS3 Simulations of Indoor Hydrocarbon Fires Engulfing Radioactive Waste Packages
Wenzel Brücher, Marina Röwekamp, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS)
mbH
Thermal Testing of Type B Packages in Furnaces per ASTM Standard Practice E 2230
Matthew Feldman P. T. Singley, R. D. Michelhaugh, M. B. Hawk, Larry B. Shappert, Oak
Ridge National Laboratory
The Use of CAFE-3D for the Simulation of Tunnel Fires
Carlos Lopez, Sandia National Laboratories; Ahti Suo-Anttila, Alion Science and Technology;
Jorman A. Koski, Consultant to Sandia National Laboratories
Spent Fuel Transportation Cask Response to a Tunnel Fire Scenario
Harold E. Adkins Jr., Pacific Northwest National Laboratories; Christopher Bajwa, United
States Nuclear Regulatory Commission
12:30 p. m. – 1:30 p. m. Lunch break
1:30 p. m. – 6:00 p. m. Technical Tour
BAM drop test facility Horstwalde (50 km south of Berlin). The drop test facility is currently
under construction to be ready for operation before PATRAM 2004. For this technical tour a 9
m drop of a big full-size spent fuel transport and storage cask (GNB-CONSTOR V/TC, 185
tons) is planed to be performed.
Wednesday, September 22, 2004
8:30 a. m. – 9:00 a. m.
3.0
Plenary (TBD)
9:10 a. m. – 10:10 p. m.
3.1 Review and Implementation of IAEA Regulations - 1
17
Some Views on the Two Years Review/Revision Cycle of the IAEA „Regulations for the
Safe Transport of Radioactive Material”
Christel Fasten, Frank Nitsche, Federal Office for Radiation Protection
The Good, the Bad, and the Ugly of the Two Year Review Cycle
Felix M. Killar Jr., Nuclear Energy Institute
The Future of the Transport Regulations
Richard Boyle, US Department of Transportation
3.13 Panel Discussion on this Topic 3:30 p. m. – 5:00 p. m.
3.2 Quality Assurance - 1
Would You Procure Radioactive Waste Containers Without a Supplier Quality
Evaluation?
Ashok Kapoor, US Department of Energy, Ron Natali, LLNL, Mark Hawk, ORNL
US Nuclear Regulatory Commission Quality Assurance Roles and Responsibilities for
Radioactive Material Transport
Robert Temps, US Nuclear Regulatory Commission
Customer Satisfaction Techniques Applied to the Transport of Nuclear Fuels to Meet
ISO 9001:2000 Requirements.
G. K. Fisher, BNFL
3.3 Back End Storage and Transport - 1
Operational Experience of Castor 440/84 in Dukovany NPP
Stanislav Kuba, CEZ, a.s.
Radiation Exposure During Spent Fuel Transfer and Storage at CNE-PROD Cernavoda
NPP
Iona Elisabeta Daian, Ion Popescu, Vasile Simionov, CNE-PROD Cernavoda NPP
Operational Experience of On-Site Transport Of Spent Nuclear Fuels in Korea
Heung-Young Lee, Sung-Hwan Chung, Chang-Yeal Baeg, Byung-II Choi, KHNP; Yong-Jae
Kim, KINS
3.4 Structural Response Assessment by Analysis
Dynamic Calculation of TN 28 VT Package During 9 Meter Drop
Pascal Goude, Jürgen Werle, Badéa Martinotti, Laurent Milet, Cogema Logistics (Areva
Group)
18
Analyses to Demonstrate the Structural Performance of the CASTOR KN-12 in
Hypothetical Drop Accident Scenarios
Rudolf Diersch, M. Weiss, Gesellschaft für Nuklear-Behälter (GNB); Chi-Fung Tso, Arup; S.H. Chung, H. Y. Lee, KHNP
Numerical Simulations of Dynamic Deformation of Transport Spent Fuel Package in
Accidental Impact Loads
Alexander Ryabov, Vladimir Romanov, Sergey Skurikhin, Scientific Consulting Company
“SarovLabs”
10.10 a.m. – 10.30 a.m. Coffee break
10:30 a. m. – 12:10 p. m.
3.5 National Implementation of IAEA Regulations
Regulatory Requirements for the Transport of Radioactive Materials in Canada
Rajesh Garg, Canadian Nuclear Safety Commission
Security of the Radioactive Materials During Transportation in the Lithunia
Tenatas Sumskis, Radiation Protection Centre
Improvement of Transport Regulations for Radioactive Material in Korea
Yong-Jae Kim, Bok-Hyung Lee, Kyung-Ho Chun, Korea Institute of Nuclear Safety (KINS)
New Basic Safety Regulations of Radioactive Material Transport in Russia
Vladimir Ershov, M. O. Shvedov, Department of Safety, Ecology and Emergency Situations of
Minatom of Russia; V. N. Ershov, FGUP” Emergency Response Center of Minatome of
Russia”; S. A. Ulanov, Federal Supervision of Russia for Nuclear and Radiation Safety
Transport of Radioactive Material in Bangladesh: A Regulatory Perspective
Abdus Sattar Mollah, Bangladesh Atomic Energy Commission
3.6 Quality Assurance - 2
Quality Assurance, Fabrication, and Accompanying Quality Control of CASTOR
Transport and Storage Casks
Martin Beverungen, Reiner Laug, Gesellschaft für Nuklear-Behälter (GNB)
Surveillance of the Quality Assurance in Manufacturing of Spent Fuel and HLW
Transport- and Storage Casks
Manfred Baden, TÜV Rheinland Group; Thilo Nitz, Bundesanstalt für Materialforschung und –
prüfung (BAM)
19
Quality Assurance in Production and Use of Special Form Radioactive Material - Focal
Points in BAM Approval
Annette Rolle, Lothar Buhlemann, Bundesanstalt für Materialforschung und –prüfung (BAM)
Focusing on the Environment
Daniel Lacroix, Caroline Mollat, Laurent Hansel, Cogema Logistics (Areva Group)
Corrosion Protection of Containers for Radioactive Waste - Requirements of storage
Axel Schmidt, G. Hasemann, F. Vollmer, TÜV Hannover/Sachsen-Anhalt e.V.
3.7 Waste Packages
Development of a Type B Package for Radioactive Waste
Sung-Hwan Chung, Byung-II choi, Jong-Bae Lee, Heung-Young Lee, KHNP; Ki-Seog Seo,
KAERI
The New Generation of the MOSAIK Casks
Dieter Brüning, S. Bauriedel, Gesellschaft für Nuklear-Service (GNS); Frank Jonas,
Bundesanstalt für Materialforschung und –prüfung (BAM)
Transport Concept of New Waste Management System (Inner Packaging System)
Kenichi Hakozaki, Transnuclear, Ltd; Ryutaro Wada, Kobe Steel, Ltd.
Optimised Concrete Containers for Waste Management
Karl-Heinz Kramm, Wolfgang Steinwarz, Reiner Wienert, Siempelkamp Nukleartechnik GmbH
The Development of a Type B (U) Transport Container Design in Cast and Forged
Stainless Steel for the Transport of Immobilised Intermediate Level Waste
Bill Sievwright, UK NIREX; P. Dixon, REW Nukem
3.8 Criticality
Criticality Assessment of Fuel Assemblies with Missing Fuel Rods - An intractable
Problem?
Franz Hilbert, Nuclear Cargo + Service GmbH
Nuclear Criticality Safety Analysis for the Traveller PWR Fuel Shipping Package
Peter J. Vescovi, Norman Kent, Westinghouse Electric Company; Carlos C asado
Expansion of the Capabilities of the GA-4 Legal Weight Truck Spent Fuel Shipping
Cask
Alan Zimmer, General Atomics
Status of Burnup Credit for Transport of SNF in the United States
Cecil Parks, J. C. Wagner Oak Ridge National Laboratory
Harmonisation of Criticality Assessments of Packages for the Transport of Fissile
Nuclear Fuel Cycle Materials
Lyn M. Farrington, World Nuclear Transport Institute (WNTI)
20
12:10 p. m. – 1:30 p. m. Lunch break
1:30 p. m. – 3:10 p. m.
3.9 Guidance on Package Approval
Revised Guidelines for the Approval Procedure of Package Designs in Germany
Frank Nitsche, Federal Office for Radiation Protection; Roland Rödel, Bundesanstalt für
Guidance for Package Approvals in the United Kingdom
Edmund Morgan-Warren, Department of Transport
The Advantages of using Standardized Review Procedures in Certifying Type B
Radioactive Material Packages
Earl Easton, US Nuclear Regulatory Commission; Sylvain Faille, Canadian Nuclear Safety
Commission
Benefits of Standard Format and Content for Approval of Packaging for Radioactive
Material
David Pstrak, N. Osgood, US Nuclear Regulatory Commission
Aspects of Safety Assessments for Package Designs with Additional Equipment
Components
Ingo Reiche, Federal Office for Radiation Protection; Torsten Krietsch, Bundesanstalt für
3.10 Specific Package and Design Aspects
CASTOR HAW28M - a High Heat Load Cask for Transport and Storage of Vitrified High
Level Waste Containers
André Voßnacke, Karl Klein, Bernhard Kühne, Gesellschaft für Nuklear-Behälter (GNB)
Development of the Package Design TNB170
Christophe Courtois, Herman Sannen, Transnubel
The NCS 45 Cask Family: an Updated Design Replaces an Old Design - Lessons
Learned During Design, Testing and Licensing
Wolfgang Bergmann, Franz Hilbert, Nuclear Cargo + Service GmbH
Enhanced Safety Margins During Wet Transport of Irradiated Fuel by Catalytic
Recombination of Radiolysis Hydrogen and Oxygen
Julian T. Spencer, Nicholas A. Hodge, Mark Bankhead, BNFL
Tie-Down Assessment of Radioactive Material Packages on Conveyances - Approach
to Competent Authority Approval Applications in accordance with TS-R 1 (June 2000)
and TS-G-1.1 (June 2002)
John Read, Arup
21
3.11 Spent Fuel Transports
Facilities and Systems for Transport of Encapsulated Spent Fuel to a Final Repository
in Sweden
Peter Dybeck, SKB
Development of Spent Fuel Transport System and First Shipment in China
Zhimin Qu, Yiaoqing Li, Everclean Environmental Engineering Corp.
BWR Spent Fuel Transport and Storage System for KKL TNTM52L / TNTM97L / TNTM24
BHL
Damien Sicard, A. Verdier, Cogema Logistics (Areva Group), P.-A. Monsigny, NOK/KKL
Lessons Learned from the West Valley Spent Nuclear Fuel Shipment In the United
States
Michael Tyacke, Idaho National Engineering and Environmental Laboratory
BWR-Spent Fuel Transport and Storage with the TN9/4 & TN24 BH Casks
Lise Wattez, Cogema Logistics (Areva Group); Yves Marguerat, BKW FMB Energy Ltd.
3.12 Shielding and Dose Assessment
Shielding Analysis of a Transport and Storage Cask for Spent BWR Fuel - Applicability
of the Code SAS4 and Discussion of Results
Franz Hilbert, Nuclear Cargo + Service GmbH; Makoto Morishima, Hiroki Tamaki, Mitsubishi
Heavy Industries
Radiation Shielding Analysis of a Spent Fuel Transport Cask with an Actual
Configuration Model Using the Monte Carlo Method - Comparison with the Discrete
Ordinates Sn Method Kohtaro Ueki, Kenji Sasaki, Advanced Reactor Technology Co., Ltd
Performance of the Improved Version of Monte Carlo Code A3MCNP for Cask Shielding
Design
Yusuke Miyake M. Ohmura, T. Hasegawa, Mitsubishi Heavy Industries, Ltd.; K. Ueki, Tokai
University, O. Sato, Mitsubishi Research Institute, A. Haghighat, G. E. Sjoden, Department of
Nuclear and Radiological Engineering, University of Florida
Comparison of Dose Rates Calculations with Measurements at a CASTOR HAW 20/28
CG CASK
Frank-Michael Börst, Ingo Reiche, Holger Thile, Federal Office for Radiation Protection
A Comparison of Dose Rate Measurement and Assessment that Enabled the Capacity
of a Spent Fuel Flask to be Increased
Michael Dean, BNFL
22
3:10 p. m. – 3:30 p. m. Coffee break
3.13 Review and Implementation of IAEA Regulations - 1
3:30 p. m. – 5:00 p. m.
Panel Discussion
3:30 p. m. – 6:00 p. m.
3.14 Special Session - Posters
Packagings / Cask Systems
The Cask with Uranium Radioactivity Shield for the Air Transportation of Radio-Isotope
Commodity
Yury Metelkin, Alexey Visik, Bochvar Institute of Inorganic Materials and SRINR
Inspection of Gamma Radiography Projectors for Reloading and Transportation
Purposes
Yasko Kodama, F. F. Suzuki, D. L. Rodrigues, CNEN/SP Japan; J. R. da Camara, CNEN/SP
Brazil
Bringing Russian Cask Fleet for Nuclear Fuel Transport in Correspondence with IAEA96 Requirements for Air Nuclear Material Transport
V. I. Duday, R. I. Il´kaev, A. D. Kovtun, Vitaly Z. Matveev, A. I. Morenko, V. M. Nikulin, V. I.
Shapovalov, V. A. Yakushev, RFNC-VNIIEF; V. C. Bobrovski, Public corporation “Engineering
plant”; V. V. Rogkov, Public corporation “Novosibirsk plant of chemical concentrates”; A. M.
Agapov, Safety, Ecology and Extraordinary situation Department of Minatom, A. S.
Kolesnikov, Russian state atom-inspection
Regulatory Inspection for Spent Fuel Transport using KN-12 Packaging in KOREA
Lee Bok Hyoung, Jeon Kyung Ho, Jo Woon Gap, Kim Kyung Hwa, Korea Institute of Nuclear
Safety (KINS)
„MOSAIK“ 20 Years of Experience with a Cask System for Transportation, Conditioning
and Storage of Radioactive Waste
Gert Gestermann, Gesellschaft für Nuklear-Service (GNS)
A Perspective on R&D Program for Spent Fuel Interim Storage Cask System
Tomofumi Yamamoto, Kunio Maruoka, MHI, Nuclear Energy Systems Headquarters; Syuhei
Kuri, Hiroki Tamaki, MHI, Kobe Shipyard and Machinery Works
23
Use of CASTOR and CONSTOR Casks for RBMK and VVER Fuel Assemblies
Rudolf Diersch, Gesellschaft für Nuklear-Behälter (GNB); Felix Thomas
Design of a New MOX Powder Transport Packaging to Support FBR Cycle
Development Mission
Kiyoaki Yamamoto, K. Shibata, Y. Ouchi, T. Kitamura, Japan Nuclear Cycle Development
Institute; Y. Kamino, T. Take, Kimura Chemical Plants Co., Ltd.
NUHOMS-MP197 Transport Cask
Peter Shih, Transnuclear, Inc.
Absorbent for Application in a Package for Liquid Radioactive Isotope for Medical
Kyoung Sik Bang, S. P. Lim, J. C. Lee, H. S. Shin, K. S. Seo, Korea Atomic Energy Research Institute
Full-Scale Prototyping of the Hitachi Dual-Purpose Metal Cask and Verification of its
Heat Transfer Characteristics
Naoki Kumagai, Naoyuki Ishida, Masaya Ootsuka, Mamoru Kamoshida, Takeshi Hiranuma, Seigo
Doumori, Tadahiro Hoshikawa, Masashi Shimizu, Jun Kashiwakura, Makoto Hayashi, Hitachi Ltd.
Metallurgical Concept for Maximized Use of Recycled Scrap in the Production of
Storage Packages
Wolfgang Kleinkröger, Dieter Bounin, Siempelkamp Giesserei
ES-3100: A New Generation Shipping Container for Bulk Highly Enriched Uranium and
Other Fissile Materials
Jeffrey G. Arbital, Gerald A. Byington, Dean R. Tousley, BWXT Y-12, LLC
Analysis / Computer Tools
Empirical Formulars on the Impact Forces of Impact Limiters under the 9 m Free Drop
Yong-Jae Kim, Korea Institute of Nuclear Safety (KINS); Young-Shin Lee, Chung Nam National University
Validation of CFD-Methods to Predict Heat Transfer and Temperatures during the
Transport and Storage of Casks under a Cover
André Leber, WTI GmbH; Wilhelm Graf, Roland Hüggenberg, Gesellschaft für NuklearBehälter mbH (GNB)
Study on Validation of the Thermal Calculation Method and the Applicability of the
Confinement Monitoring with Full-Scale Mock-Up Test of Concrete Cask
Daiichiro Ito, K. Fujinami, K. Yamamoto, T. Suyama, Mitsui Engineering & Shipbuilding Co. Ltd.
Calculation of Heat Removal from Interim Storage Facilities for the Dry Storage of
Spent Fuel in Dual-Purpose Casks
Werner Stratmann, Peter Hages, STEAG encotec GmbH
Safety Demonstration Analyses for Severe Accident of Fresh Nuclear Fuel Transport
Packages at JAERI
Kenji Yamada, Kouji Watanabe, Yasushi Nomura, Hiroshi Okuno, Yoshinori Miyoshi, Japan
Atomic Energy Research Institute
24
Simulation of a Drop onto a Punch of a Transport Container for Nuclear Fuel
Assemblies
Gilles Marchaud, Jürgen Werle, Cogema Logistics (Areva Group)
The Application of Fluid Structure Interaction Techniques within Finite Element
Analyses of Water-Filled Transport Flasks
Craig Smith, Stefan Stojko, Rolls-Royce Naval Marine
Framatome-ANP UO2 Fresh Fuel Transportation – Criticality Application of the IAEA
TS-R-1 Regulations
M. Doucet, N. Comte, M. Landrieu, S. Zheng, Framatome-ANP Fuel Sector
New Problems of Safe RAM Transportation
V. D. Guskov, V. I. Lazorkin, N. V. Turina, V. Y. Vasiljev, V. V. Vorontsov, KBSM
Regulations / Licensing / Standards
Transport of Radioactive Material Industry Codes of Practice for United Kingdom
Neil Carr, Bill Sievwright, TCSC UK Nirex Ltd.
Licensing of LLW Final Storage Casks as Transport Casks of Type IP for Fissile
Radioactive Material
Wolfgang Bergmann, Nuclear Cargo + Service GmbH; R. Baumann, Siemens AG; H. Grunau,
Eisenwerk Bassum mbH
The Transport of Radioactive Material with Subsidiary Risks
Reinhard Pech, GUC
Standards for Transport and Storage Components established by The Atomic Energy
Society of Japan and The Japan Society of Mechanical Engineers
Makoto Hirose, Nuclear Fuel Transport Co., Ltd.; M. Aritomi, TIT; T. Saegusa, CRIEPI; T.
Hayashi, T. Takeda, TEPCO; K. Onishi, KEPCO; K. Kawakami, OCL
Current & Proposed Revisions, Changes & Modifications to American Codes &
Standards to Address Packaging, Handling, & Transportation of Radioactive Materials
& How They Relate to Comparable International Regulations
William Borter, Ccarl H. Froehlich, BNFL Fuel Solutions
Providing Radioactive Material Transportation Safety Information to the Public
John Cook, US Nuclear Regulatory Commission; Judith Espinosa, The Alliance for
Transportation Research
A Users Guide to the Interpretation of the International Atomic Energy Agency
Regulations for the Transport of Ores Containing Natural Radionuclides
Paul J. Hinrichsen, National Nuclear Regulator
25
Systems, Operations
Transport of Heavy Load Radioactive Material (Spent Fuel and High Level Waste) in
Germany
Werner Sigmund, Nuclear Cargo + Service GmbH
Laser Beam Joining of Non Oxidic Ceramics for Ultra-High Temperature Resistant
Joints
Wolfgang Lippmann, J. Knorr, R. Wolf, A.-M. Reinecke, R. Rasper, University of Technology Dresden
The System of Emergency Cards for Primary Actions in Accident at Radioactive
Material Transport in Russia
V. V. Anianiev, M. O. Shvedov, Department of Safety, Ecology and Emergency Situations of
Minatom of Russia; S. V. Ermakov, Vladimir Ershov, V. I. Stovbur, FGUP “Emergency
Response Center of Minatome of Russia”
Different Training Programs for the Transport of the Radioactive Goods Proposed by
the INSTN
Odile Kimmel, CEA INSTN
Mitigation of Cesium and Cobalt Contamination on the Surfaces of RAM Packages
James Krumhansl, Paul McConnell, Sandia National Laboratories; Ashok Kapoor, U. S. DOE
Design, Construction & Operation of a Dedicated Marine Terminal for the Transport of
Nuclear Material.
M. Zachar, BNFL; Pascal Luciani, Philippe De Place, Dunkirk Port Authority
Environmental Challenges of Decommissioning and Recycling a Nuclear Transport Ship.
T. Pearce, BNFL
Utilizing the Emergency Planning Cycle for the Transport of Radioactive Material
M. Fox, BNFL
Environmental & Technical Considerations during the Decommissioning and Recycling
of Spent Fuel Transport Flasks.
A. Finch, BNFL
Pacific Nuclear Transport Limited and British Nuclear Fuels Limited’s Experience in
Implementing Behavioral Based Safety Program as Part of the Safety Management
System for the Marine Transport of Nuclear materials
D. Billing, BNFL
Conversion of 60ft Sgns Rail Wagons: a Cost Effective Solution for Transport of
Lightweight Spent Fuel Flasks.
M. Zachar, BNFL
Equipment for RAW Handling, Packaging, Transport and Storage from ZTS VVU
KOSICE a.s.
Ladislav Vargovcik, ZTS VVU KOSICE a.s.
26
Study on Tracking System for Radioactive Material Transport
Fumitaka Watanabe, Miyuki Igarashi, Tamotsu Nomura, Japan Nuclear Cycle Development
Institute; Yoshihiro Nakagome, Research Reactor Institute
Quality Assurance and Product Quality
Daniel Lacroix, Cogema Logistics (Areva Group)
Maximizing Allowable Cask Payloads using Zone-Loading and Cooling Table
Specifications
James Hopf, Timothy Lioyd, BNFL Fuel Solutions Corporation
Reshaping Transport Operations to Overcome New Challenges
Francois Larari, Laurent Blachet, Cogema Logistics (Areva Group)
Transactive-20 ISO Container for Transporting Large Volumes of Intermediate Level Waste
Jon Jenkins, AEA Technology, Tony Gaffka, RWE NUKEM
Testing / NDT
Curing Time Effect on the Fraction of 60Co from Cement Matrix
Ilja B. Plecas, Institute of Nuclear Sciences “Vinca”
Decrease of Reaction Force of Metal Gaskets just after Initial Tightening
Hiroshi Akamatsu, Jun Shimojo, Kenichi Mantani, Keiji Morikawa, Kobe Steel, Ltd.; Hiroaki
Taniuchi, Dai Yokoe, Transnuclear Tokyo
Half and Full Scale Drop Tests for Qualification of CONSTOR Casks as Type B(U)F
Packages
Sabine König, Rudolf Diersch, Gesellschaft für Nuklear-Behälter (GNB)
The New BAM Drop Test Facility for Big Full Scale Casks
Karsten Müller, Mathias Minack, Bernhard Droste, Bundesanstalt für Materialforschung und –
prüfung (BAM)
Nondestructive Testing (NDT) as a Component of the Quality Surveillance at the
Production and the Use of the Type B-Packaging
Uve Günther, TÜV Rheinland Group, Roland Rödel, Bundesanstalt für Materialforschung und
–prüfung (BAM)
Importance of Strain and Acceleration Measurements during Drop Tests for Safety
Analysis and Package Design Optimization
Thomas Quercetti, Karsten Müller, Bundesanstalt für Materialforschung und –prüfung (BAM)
Radiation Exposure / Dose Risk / Criticality
Corrosion Behaviour of Borated Aluminium Used as Neutron Absorber
Roland Emmerich, EaglePicher Technologies GmbH; W. Ensinger, B. Enders, PhilippsUniversity of Marburg
27
Evaluation of Radiation Shielding Performance in Sea Transport of Radioactive
Material by using Simple Calculation Method
Naoteru Odano, Seiki Ohnishi, Department of Maritime Safety, National Maritime Research
Institute
Permeation Analysis of Tritium through the Titanium Hydride Storage Vessel
Kwang-Rag Kim, M. S. Lee, S. Paek, D. H. Ahn, S. P. Yim, H. Chung, Korea Atomic Energy
Research Institute
Radiation Exposure of the Environment of Interim Storage Facilities for the Dry Storage
of Spent Fuel in Dual-Purpose Casks
Birgit Wortmann, Werner Stratmann, STEAG encotec GmbH
Critically Evaluation of BWR MOX Fuel Transport Packages using Average PU Content
Christophe Mattera, Cogema Logistics (Areva Group)
A Simple Method to Determine the Re-Suspension Rate for Non-Fixed Surface
Contamination
Oliver Nolte, Wolfgang Koch, Fraunhofer ITEM; Florentin Lange, Reinhard Martens,
Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH
8:30 a. m. – 9:00 a. m.
4.0
Plenary (TBD)
9:10 a. m. – 10:10 a. m.
4.1 Thermal and Impact Protection
Thermal Assault and Polyurethane Foam Evaluating Protective Mechanisms
Charles Williamson, Zelda L. Iams, General Plastics Manufacturing Company
Shock Absorbing Evaluation of Rigid Polyurethane Foam and Styrofoam Applied to the
Small Transportation Package
Ki Seog Seo, Ju Chan Lee, Kyung Sik Bang, Korea Atomic Energy Research Institute; Sung
Hwan Jung Byung ill Choi, Korea Hydro and Nuclear Power Co. Ltd.
28
4.2 Transport Experience HLW
10 Years of Transport of Vitrified HLW from Cogema la Hague
Badéa Martinetti, Jérôme Lancelot, Cogema Logistics (Areva Group); Florence Tourneux,
Cogema (Areva Group)
Shipments of Vitrified High-Level Radioactive Waste from France to Germany as
Routine Shipments with Special Train Service
Ulrich Alter, Bundesministerium für Umwelt, Naturschutz u. Reaktorsicherheit
12-cask-transport for vitrified high level waste (HLW)
Antoine Verdier, Jérôme Lancelot, Olivier Bartagnon, Cogema Logistics (Areva Group), Astrid
Gisbertz, Wilhelm Graf, Gesellschaft für Nuclear-Service (GNS)
4.3 Development and IAEA Regulations
Historical Background of the Development of Various Requirements in the International
Regulations for the Safe Packaging and Transport of Radioactive Material
Ronald B. Pope, Consultant
The IAEA Transport Safety Appraisal Service (TranSAS)
Gerardus Johannes Dicke, International Atomic Energy Agency
The Vital Role of Industry in Contributing to the Regulatory Regime
G. Owen, BNFL
4.4 Structural Assessment Methods
Competent Authority Requirements and Developments in Finite Element Methods
(FEM) Application for Package Design Testing
Holger Völzke, Günter Wieser, Uwe Zencker, Viktor Ballheimer, Bundesanstalt für
Materialforschung und -prüfung (BAM)
Evaluation of FEM Codes for Demonstrating the Performance of RAM Packages in
Hypothetical Accident Drop Scenarios
Chi-Fung Tso, Arup, Roland Hüggenberg, Gesellschaft für Nuklear-Behälter mbH (GNB)
Concept of Stress Limitation for CASTOR Casks made of Ductile Cast Iron
Roland Hüggenberg, K. Klein, J. Holub, Gesellschaft für Nuklear-Behälter (GNB)
10.10 a.m. – 10.30 a.m. Coffee break
10:30 a. m. – 12:10 p. m.
29
4.5 Risk Assessment – 1 – Normal Conditions
Annual Collective Dose due to Transport of LSA Materials in India
Krishna Upadhyay, S. P. Agarwal, Atomic Energy Regulatory Board
Statistics on the Traffic of Radioactive Material, and the Resulting Radiation
Exposures, in the European Union and Applicant Countries
Stuart Hughes, National Radiological Protection Board; M. T. Lizot, IRSN, S. Trivelloni, APAT;
G. Schwarz, GRS; J. van Hienen, NRG
Radiation Safety in Sea Transport of Radioactive Material in Japan
Naoteru Odano, Department of Maritime Safety, National Maritime Research Institute;
Hiroyuki Yanagi, Transport Department, Nuclear Fuel Transport Co. Ltd.
Radiation Exposures of Workers and the Public Associated with the Transport of
Radioactive Material in Germany
Günther Schwarz, Hanns-Josef Fett, Florentin Lange, Gesellschaft für Anlagen- und
Reaktorsicherheit (GRS) mbH
Assessing Exposure to the Public from Low Level Radioactive Waste (LLW) Truck
Transportation in the United States to the Nevada Test Site
David S. Shafer, Scott Campbell, Bruce W. Church, Karen J. Gray, Barbara Holz, J. J. Miller,
Desert Research Institute (DRI), University System of Nevada
4.6 Selected Issues of IAEA Regulations
How Safe is Safe Enough
Bruno Desnoyers, Y. Chanzy, Cogema Logistics (Areva Group)
IAEA’S Transport Regulations: Multilateral Approval and Revision of Competent
Authority Approval Certificates
J.R. López Vietri, N. Capadona, Nuclear Regulatory Authority
Grandfathering of Competent Authority Approved Packages
Nancy L. Osgood, US Nuclear Regulatory Commission
Type B Activity Limits for Air Transport - (An Examination of Special Form and NonSpecial Form limits)
Phillip Eyre, Canadian Nuclear Safety Commission
ST - 1 or UN “Orange Book” Mexican Trucking Industry Point of View
Tomas Martinez Lopez, Mexican Chamber of Trucking Industry
30
4.7 Uranium and MOX Packages
Design, Development and Production of the TNF-XI New Powder Package
Philippe Naigeon, Stéphane Brut, Cogema Logistics (Areva Group); Tohru Fujiwara, Nuclear
Fuel Industries, Ltd.; Michael E. Cohen, Packaging Technology, Inc.
The Traveller: A New Look for PWR Fresh Fuel Packages
Brian Bayley, William E. Stilwell, Norman Kent, Westinghouse Electric Company
Development of a European MOX Package -BNFL M4/12 Projects
Bernard R. Kaye, BNFL
New Package Systems for EDF Recycling Policy
Antoine Froment, L. Michels, F. Derlot, O. Plessy, Cogema Logistics (Areva Group); C.
Penoty, EDF
Analysis of Risk and Dose when Using Thermal Protection on Non-Fissile and FissileExcepted UF6 48-inch Cylinder Packages
C. Green, Cameco Corporation, Elizabeth Darrough, Consultant
4.8 Non Regulatory Impact Performance
Safety Analysis of Casks under Extreme Impact Conditions
Günter Wieser, Linan Qiao, Holger Völzke, Dietmar Wolff, Bernhard Droste, Bundesanstalt für
A Method to Simulate an Airplane Strike on Dry Storage Casks: The Case of the HiSTORM MPC Storage System
K.P. Singh, A.I. Soler, J. Zhai, Holtec International
Demonstration of Impact Performance of the Nuclear Transport Package in On-site
Hypothetical Collision Scenarios by a Heavy Goods Vehicle
Chi-Fung Tso, Conrad Izatt, Arup; Mike Lacey, Rolls Royce Marine Power
Demonstrative Drop Tests of Transport and Storage Full-Scale Canisters with High
Corrosion-resistant material
Koji Shirai, T. Saegusa, Central Research Institute of Electric Power Industry
1/3 Scale Spent Fuel Canister Drop Tests Assuming Canister Handling Operation
T. Ohama, Kansai Electric Power; Ganji Abe, K. Asada, U. Saito, K. Murakami, K. Matsunaga,
Mitsubishi Heavy Industries, Ltd.
12:10 p. m. – 1:30 p. m. Lunch break
31
1:30 p. m. – 3:30 p. m.
4.9 Risk Assessment – 2 – Accident Conditions
Postulated Accident Scenarios For The On-Site Transport of Spent Nuclear Fuel
Greg Morandin, Richard Sauvé, Atomic Energy of Canada Ltd.
Determination of Accident Related Release Data
Wolfgang Koch, Oliver Nolte, Fraunhofer ITEM; Florentin Lange, Reinhard Martens,
Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH
Spent Fuel Transport Associated with other Dangerous Goods in Regular Train Units Assessment of Hypothetical Explosion ImpactsBernhard Droste, Viktor Ballheimer, Bundesanstalt für Materialforschung und -prüfung (BAM)
Package Performance Evaluation: Our Last 10-Year Experience
Pierre Malesys, COGEMA LOGISTICS (AREVA Group)
Radioactive Materials Transport Accident Analyses
Thomas I. McSweeney, S. J. Maheras, S. B. Ross, Battelle Memorial Institute
4.10 Contamination
Developments in Spent Fuel Transport in Germany
Beate Kallenbach-Herbert, Oeko-Institut e.V.; Florentin Lange, Gesellschaft für Anlagen- und
Reaktorsicherheit (GRS) mbH
Experience with Contamination Protection of Spent Fuel Transport Packages in
Germany since 2000 / 2001
J. Seidel, E.ON Kernkraft; P. Jung, EnBW-KKP; H. Krinninger, R. Bach, ACTA Technologien
A Risk-Informed Basis for Establishing Non-Fixed Surface Contamination Limits for
Spent Fuel Transportation Casks
Richard R. Rawl, Oak Ridge National Laboratory; John Cook, US Nuclear Regulatory
Commission
A Model to Determine the Radiological Implications of Non-fixed Radioactive
Contamination on the Surfaces of Packages and Conveyances
Stuart Hughes, S. M. Warner Jones, National Radiological Protection Board; M. T. Lizot, M.-L.
Perrin, IRSN; S. Thierfeld, Brenk Systemplanung GmbH; E. Schroedl, G. Schwarz, GRS;R.
Rawl, ORNL; M. Munakata, JAERI; M. Hirose, NFT Co. Ltd.
A Model for the Derivation of New Transport Limits For Non-Fixed Contamination
Stefan Thierfeldt, Brenk Systemplanung, Bernd Lorenz, Johannes Hesse, Gesellschaft für
Nuklear-Behälter (GNB)
32
4.11
Containment and Seals
The Use of Dual Material Seals for Packaging
Charles J. Temus, Joseph C. Nichols III, Packaging Technology Inc.
A General Approach for Quantifying the Heat-Ageing of Seals
Andre Régis, Pierre Malesys, Cogema Logistics (Areva Group)
TN-FLEX: a New Generation of Fluorocarbon O-Rings Developed by COGEMA LOGISTICS with Enhanced Characteristics at Low Temperature (-40°C)
Hervé Issard, Régis Andre, Cogema Logistics (Areva Group)
EPDM and Fluorocarbon Seal Materials: A Comparison of Performance for Nuclear Fuel
Transport Flasks.
Terry Chivers, BNFL Magnox Generation; Alan George, British Energy Generation Ltd
A Guide to the Suitability of Elastomeric Seal Material for Use in Radioactive Material
Transport Packages
Danny Vince, Dept. For Transport
4.12
Front End Materials and MOX
Transport of UF6 in Compliance with TS-R-1
Ben Dekker, World Nuclear Transport Institute (WNTI)
Transport Experience of New TNF-XI Powder Package
Ichiro Nomura, Tohru Fujiwara, Nuclear Fuel Industries; Philippe Naigeon, Cogema Logistics
Transport of Natural UF6 in a Challenging Environment
Pascal Chollet, Cogema Logistics (Areva Group)
Observations and Suggestions for Improved Transport/Packaging Approvals
Charles Vaughn, Global Nuclear Fuel
25 Years of Transport Experience of Fresh MOX Fuel Assemblies for ATR “Fugen”
Kiyoaki Yamamoto, S. Takahashi, S. Inose, S. Uchida, A. Hayashi, W. Yuasa, Japan Nuclear
Cycle Development Institute
Fresh MOX Fuel Transport in Germany: Experience for using the MX6
Thierry Lallemant, Cogema Logistics (Areva Group); Luc Marien, FBFC-I; Roland Wagner,
RWE; Werner Jahreiss, Framatome ANP GmbH; Horst Tschiesche, NCS
3:10 p. m. – 3:30 p. m. Coffee break
33
3:30 p. m. – 5:10 p. m.
4.13 Impact Assessment – IAEA or Extraregulatory?
The Relevance of the IAEA Tests to Severe Accidents in Nuclear Fuel Cycle Transport
William Wilkinson, World Nuclear Transport Institute (WNTI)
Package Performance Study: Developments since PATRAM 13
Andrew J. Murphy, Bret A. Tegeler, Amy Snyder, Robert Lewis, US Nuclear Regulatory
Commission; Ken Sorenson, Sandia National Laboratories
4.15 p.m. – 05.00 p.m. Panel Discussion on this Topic
4.14 Low Risk Materials
Development of an Improved Radiological Basis and Revised Requirements for the
Transport of LSA/SCO Materials
Iain Gray, RM Sonsultans Ltd; F. Lange, Eugen Hoermann, GRS; Neil A. Carr, Nirex
Transportation Safety Aspects of Ore and Related Material Progeny and Exemptions
Richard R. Rawl, Keith F. Eckermann, Oak Ridge National Laboratory; John Cook, US
Nuclear Regulatory Commission
Transport Regulation of NORM - a Threat to the Industry?
Ernst Joachim Martin, TIC, Tantalum-Niobium International Study Center
The Transport of Radiopharmaceuticals in the United States
Fred Ferate, US Department of Transportation
Large Component Regulatory Relief in the United States
James L. Williams, Richard W. Boyle, US Department of Transportation
4.15 Gamma Shielding Materials
Development of New Type Concrete for Spent Fuel Storage Cask
Jun Shimojo, K. Mantani, Kobe Steel, Ltd.; E. Owaki, Y. Sugihara, A. Hata, M. Shimono,
Taisei Corporation, H. Taniuchi, Transnuclear, Ltd.
Mechanical and Corrosion Behaviour of Encapsulated Shielding-Concrete CONSTORIT
in the CONSTOR Wall - Test Program and First Results Hans-Peter Winkler, Gesellschaft für Nuklear-Behälter (GNB); Eva Herzog
Characteristics and Fabrication of Cermet Spent Nuclear Fuel Casks: Ceramic Particles
Embedded in Steel
Charles Forsberg, Oak Ridge National Laboratory
34
Process of Production of Cermet Based on DUO2 - Steel in Cold Crucible Induction
Melter to be Used as Protective Material for Spent Nuclear Fuel Container’s Structures
V. T. Gotovchikow, Victor A. Seredenko, B. S. Mironov, All-Russian Research Inst. Of
Chemical Technology
4.16 Structural Response and Fuel Rods
Testing of Light Water Reactor Fuel Rods to Support Criticality Safety Analysis of
Transport Accident Conditions
Peter C. Purcell, BNFL; M. Dallongeville, Cogema Logistics
Fuel Integrity Project: Analysis of Light Water Reactor Fuel Rods Tests Results
Maurice Dallongeville, Jürgen Werle, Cogema Logistics (Areva Group); Gerard McCreesh,
BNFL
High Burn-up Spent Nuclear Fuel Structural Response when Subjected to a
Hypothetical Impact Accident
Mahendra J. Shah, Daniel T. Huang, Jack Guttmann, US Nuclear Regulatory Commission;
Harold E. Adkins, Carl E. Beyer, Nicholas A. Klymyshyn, Brian J. Koeppel, Pacific Northwest
National Laboratory
The Buckling of Fuel Rods in Transportation Casks under Hypothetical Accident
Conditions
Gordon Bjorkman, US Nuclear Regulatory Commission
A Methodology for the Evaluation of Fuel Rod Failures under Transportation Accidents
Joseph Rashid, ANATECH
7:00 p.m. – 10:00 p. m. Banquet
8:30 a. m. – 9:00 a. m.
5.0
Plenary (TBD)
35
9:10 a. m. – 10:30 a. m.
5.1 Emergency Response - 1
Emergency Response Arrangements for the Transport of Radioactive Materials
Edmund Morgan-Warren, Department of Transport
Development of Supporting System for Emergency Response to Maritime Transport
Accidents Involving Radioactive Material
Naoteru Odano, Department of Maritime Safety, National Maritime Research Institute; Hiroshi
Suzuki, Safety Science and Police Department, Mitsuhishi Research Institute, Inc.
Emergency Preparedness & Response in Case of a Fire Accident with (UF6) Packages
Tracking Suez Canal
Mohamed Salama Dr., Atomic Energy Authority
5.2 Neutron Shielding Materials
Thermal Behaviour of Neutron Shielding Material, Resin-NS-4-FR, under Long Term
Storage Conditions
Nobuyuki Yamada, Akio O-iwa, Ryoji Asano, Hitachi Zosen Diesen and Engineering Co., Ltd,
Nuclear Development Dept.; Ryuichi Horita, Hitachi Zosen Corp. Research Laboratory
Development of a New Neutron Shielding Material, TN Resin Vyal, for
Transport/Storage Casks of Radioactive Materials
Pascale Abadie, Cogema Logistics (Areva Group)
Behaviour of Neutron Moderator Materials at High Temperatures in CASTOR Casks Qualification and Assessment
Torsten Krietsch, Dietmar Wolff, Bundesanstalt für Materialforschung und –prüfung (BAM);
Ulrich Knopp, Gesellschaft für Nuklear-Behälter (GNB); Hans-Dieter Brocke, TÜV Rheinland
Group
5.3 Back End Storage and Transport - 2
Safe Transport of Spent Fuels after Long-Term Storage
Masanori Aritomi, Tokyo Institute of Technology; Tomoyuki Takeda, Tokyo Electric Power
Company; Susumu Ozaki, OCL Company Ltd.
Integrity Assessment of Dual-Purpose Metal CASK after Long Term Interim Storage Seal Performance under Transport Conditions
H. Kawakami, N. Uchiyama, M. Yasuda, S. Matsuoka, Takeshi Yokoyama, Japan Nuclear
Energy Safety Organisation
36
Safety Aspects of Long-term Dry Interim Storage of Type-B Spent Fuel and HLW
Transport Casks
Dietmar Wolff, Holger Völzke, Bernhard Droste, Roland Rödel, Bundesanstalt für
Cask Operation and Maintenance for Spent Fuel Storage
Jae Sol Lee, International Atomic Energy Agency
5.4
Closures
Bolt Study - Behaviour of Bolts in Drop Accident Scenarios of the Nirex 3M3 Box ILW
Package
Gordon Turner, UK Nirex Ltd.; Chi-Fung Tso, Arup
Improved Bolt Models for Use in Global Analyses of Storage and Transportation Casks
Subject to Extra-Regulatory Loading
Robert J. Kalan, Douglas J. Ammerman, Kenneth W. Gwinn, Sandia National Laboratories
Thermo-Mechanical Finite Element Analyses of Screwed Cask Lid Structures
Günter Wieser, Linan Qiao, Arno Eberle, Holger Völzke, Bundesanstalt für Materialforschung
und -prüfung (BAM)
Containment Performance of Transportable Storage Casks at 9 m Drop Test
Hitoshi Tobita, Hitachi Zosen Corp.; Kenji Araki, Hitachi Zosen Diesel and Engineering Co.,
Ltd
10:30 a. m. – 10:50 a. m. Coffee break
10:50 a. m. – 12:10 p. m.
5.5
Emergency Response - 2
Plutonium Ocean Shipment Safety Between Europe and Japan
J.D. Pierce, G. F. Hohnstreiter, J. D. McClure, J. D. Smith, R. J. Dukart, J. A. Koski, J. W.
Braithwate, N. R. Sorenson, Sandia National Laboratories; K. Yamamoto, T. Kitamura, K.
Shibata, Y. Ouchi, T. Ito, Japan Nuclear Cycle Development Institute
Assessment of Safety Distances to be Implemented in Case of Accident in Radioactive
Material Transportation
Gilles Sert, Francoise Rancillac, Thierry Cleach, Institut de Radioprotection et de Sureté
Nucléaire
37
Japan’s Regulatory and Safety Issues Regarding Nuclear Fuel Material Transport
Toshio Saito, Nuclear and Industrial Safety Agency, Ministry of Economy, Trade and Industry,
government of Japan (GOJ); Shuzo Ishimaru, Ministry of Land, Infrastructure and Transport,
GOJ; Tsuneyasu Yamanaka, Japan Nuclear Energy Safety Organization, GOJ
Transitioning Transportation Emergency Response Preparedness Programs to
Minimize Impacts on Spent Nuclear Fuel Transport Operations
Marsha Keister, INEEL/BBWI
Emergency Response Preparedness: The French Experience of Large Scale Exercises
Daniel Chanson, B. Desnoyers, Cogema Logistics (Areva Group); Jean Marie Chabane,
DGSNR
5.6 Fissile Material Provisions
Technical Basis for Proposed Fissile Exemption Criteria for Transport Packages
Cecil Parks, C. M. Hopper, Oak Ridge National Laboratory
Derivation of Criteria for Exceptions from Criticality Safety Requirements
Dennis Mennerdahl, E Mennerdahl Systems
Selection of Exception Limits for all Actinide Nuclides Based on Revised Criteria for
Safe International Transport
Caroline Lavarenne, V. Rouyer, IRSN; D. Mennerdahl, RMS; C. Dean, SERCO; N. Barton,
Department of Transport Local Government, Radioactive Materials Transport Division; F.
Jean, APTUS
Spent Nuclear Fuel Transportation Casks Evaluation for Water In-Leakage
Mahendra J. Shah, Daniel T. Huang, Jack Guttmann, US Nuclear Regulatory Commission;
Harold E. Adkins, Carl E. Beyer, Nicholas A. Klymyshyn, Brian J. Koeppel, Pacific Northwest
National Laboratory
Criticality Safety of Spent Fuel Casks Considering Water Inleakage
Nancy L. Osgood, Carl J. Withee, Earl P. Easton, US Nuclear Regulatory Commission
5.7 Basket Design and Materials
Development of Basket for Transport/ Storage Cask Using Square Tube made of
Aluminium Alloy Containing Neutron Absorbing Materials
Katsuyuki Hayashi, Kazuo Iwasa, Hitachi Zosen Diesel and Engineering Co., Ltd; Masakazu
Iwase, Nikkei Niigata Co. Ltd.; Jun Kusui, Toyo Aluminium K. K.
Nickel-based Gadolinium Alloy for Neutron Adsorption Application in RAM Packages
Charles Robino, Paul McConnell, Sandia National Laboratories; Ron Mizia, Idaho National
Engineering & Environmental Laboratory
38
Development of High-Strength Aluminium Alloys for Basket in Transport and Storage
Cask for High Burn-up Spent Fuel
Yoshiharu Kamiwaki, Masafumi Ishii, Kobe Shipyard and Machinery Works, MHI; Yasuhiro
Sakaguchi, Takaharu Maeguchi, Takasago Research and Development Center, MHI;
Tomofumi Yamamoto, Nuclear Energy Systems Headquarters, MHI
Neutron Absorber Qualification and Acceptance Testing from the Designer’s
Perspective
William Bracey, Transnuclear, Inc.; René Chiocca, Cogema Logistics
NIBSORB: A Coating for the Production of Absorber Elements Subjected to Corrosion.
Matthias Patzelt, Metallveredlung GmbH
5.8 Heat Dissipation
Natural Ventilation of a Generic Cask under a Transport Cover - CFD and Analytical
Modelling
Gavin Davies, Chi-Fung Tso, Arup
2D and 3D Thermal Simulations for Storage Systems with Internal Natural Convection
for Canistered Spent Fuel
Mike Yaksh, Christine Wang, NAC International
Thermal Analysis of Storage Cask for 24 Spent PWR Fuel Assemblies
Ju Chan Lee, Kyung Sik Bang, Ki Seog Seo, Ho Dong Kim, Korea Atomic Energy Research
Institute; Heung young Lee, Korea Hydro & Nuclear Power Co., Ltd.
Analyses to Demonstrate the Thermal Performance of the CASTOR KN-12
Rudolf Diersch, M. Weiss, Gesellschaft für Nuklear-Behälter (GNB); Chi-Fung Tso, Arup; S.H. Chung, H. Y. Lee, KHNP
Experimental Test of Heat Transfer from Transport Casks with Axial Fins
Karl-Josef Baumgärtner Ronny Perez-Kretschmer, Gesellschaft für Nuklear-Behälter (GNB)
End of PATRAM 2004 Sessions
12:30 p. m. - 1:30 p. m. Lunch break
1:30 p. m. - 7:00 p. m. Technical Tour
BAM drop test facility Horstwalde (50 km south of Berlin). The drop test facility is currently
under construction to be ready for operation before PATRAM 2004. For this technical tour a 9
m drop of a big full-size spent fuel transport and storage cask (MHI-MSF69 BG, 131 tons) is
planed to be performed.
39

Invitation with Preliminary Programme

Transcription

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