IAEA / USA INTERREGIONAL TRAINING COURSE
on

Technical and Administrative Preparations Required for Shipment of
Research Reactor Spent Fuel to Its Country of Origin

Argonne National Laboratory
Division of Educational Programs
Argonne, Illinois, USA

13 - 24 January 1997

Course Overview and Objectives

Opening Ceremony Agenda

Course Lecturers

Course Calendar Agenda
A two-page calendar showing course activities:
For the week of 13-17 January 1997
For the week of 20-24 January 1997.

List of Course Participants, Lecturers, and Observers
Along with available addresses, telephone numbers, fax numbers, and e-mail addresses.
 

COURSE DOCUMENTS

Module 1: Background Information

L.1.1: Course Overview and Outline
Iain Ritchie, International Atomic Energy Agency

L.1.2: Status of Research Reactor Spent Fuel Worldwide:- Database Summary
Iain Ritchie, International Atomic Energy Agency

L.1.3: US Implementation Strategy for Foreign Research Reactor Spent Fuel Shipment
Kenneth Chacey, U.S. Department of Energy, USA

L.1.3a: Supplementary Images Related to L.1.3a
Kenneth Chacey, U.S. Department of Energy, USA

Module 2: Regulations

L.2.1a: IAEA Safeguards
Iain Ritchie, International Atomic Energy Agency

L.2.1b: Convention on the Physical Protection of Nuclear Material
Iain Ritchie, International Atomic Energy Agency

L.2.1c: DOE Nuclear Material Accountability
Garald Smith, U.S. Department of Energy, Idaho Operations Office, USA

L.2.1d: Physical Security Plan for Sea Shipment of IAEA Category II Foreign Spent Research Reactor Fuel
Edward Wonder, Integrated Resource Group, USA

L.2.2-3: Transportation Regulations
Richard Rawl, International Atomic Energy Agency


Module 3: Fuel Classification

L.3.1: MTR Fuel Classification
Trent Andes, Westinghouse Savannah River Company, USA

L.3.1a: Savannah River Site Appendix A Agreement Preparation Guidelines
Westinghouse Savannah River Company, USA

Appendix A Draft Form, January 1997
Appendix A Preparation Guidance
Sample Appendix A for Generic MTR Assembly
Sample MTR Assembly Drawings
Sample SRS Review Calculations

L.3.2: TRIGA Fuel Classification
Kraig Wendt, Lockheed Martin Idaho Technologies Company, USA

L.3.2a: Supplement: TRIGA Fuel Classification Spent Nuclear Fuel Data Form
(Form Available in Adobe PDF Format Only)
Kraig Wendt, Lockheed Martin Idaho Technologies Company, USA

W.3.2b: Spent Nuclear Fuel Transfer Data
Idaho National Engineering Laboratory, USA

L.3.3: Spent Fuel Classification Data
Raymond B. Pond, Argonne National Laboratory, USA

L.3.3a: PHDOSE Computer Program Package with Example Calculations
Raymond B. Pond, Argonne National Laboratory, USA

L.3.3b: ANL/RERTR/TM-25, Photon Dose Rates from Spent Fuel Assemblies with Relation to Self-Protection (Rev. 1) February 1996
Raymond B. Pond and James E. Matos, Argonne National Laboratory, USA

L.3.3c: ANL/RERTR/TM-26, Nuclear Mass Inventory, Photon Dose Rate, and Thermal Decay Heat of Spent Research Reactor Fuel Assemblies (Rev. 1) December 1996
Raymond B. Pond and James E. Matos, Argonne National Laboratory, USA

L.3.3d: Decay Heat and Residual Activity Calculations
Peter C. Ernst, Consultant, Canada


Module 4: Cask Selection

L.4.1: Cask Selection
Keith Brown, Science Applications International Company, USA


Module 5: Local Transportation Plan, Local Arrangements and Arrangements with Transit Countries

L.5.1: Local Transportation Plan and Local Arrangements
A. Francis DiMeglio, Consultant, USA

L.5.2: Overview of Local Arrangements in Japan
Fusao Nakayama, Japan Atomic Energy Research Institute, Japan


Module 6: Contracting Arrangements

L.6.1: Contracting Arrangements - Savannah River Site (SRS)
William D. Clark, U.S. Department of Energy, Savannah River Operations Office, USA

L.6.1a: Supplement: Appendix A and Appendix B Agreements
Appendix A Agreement: Spent Nuclear Fuel Acceptance Criteria
Appendix B Agreement: Transportation Package (Cask) Acceptance Criteria
William D. Clark, U.S. Department of Energy, Savannah River Operations Office, USA

L.6.1b: Example Contract Document - For Information Only "Terms and Conditions for the Acceptance of Foreign Research Reactor Spent Nuclear Fuel at the Savannah River Site"
U.S. Department of Energy, Savannah River Operations Office, USA

L.6.2: Process for Return of Foreign Research Reactor (FRR) TRIGA Spent Nuclear Fuel (SNF) to the Department of Energy Idaho
Robert Stump, U.S. Department of Energy, Idaho Operations Office


Module 7: Preparation of Procedures
L.7.1 Preparation of Procedures
Peter C. Ernst, Consultant, Canada

Module 8: Records and Reports
L.8.1 Records and Reports
Peter C. Ernst, Consultant, Canada

Module 9: Training
L.9.1 Training
A. Francis DiMeglio, Consultant, USA

Module 10: Review Prior to Shipment
L.10.1: Review Prior to Shipment
A. Francis DiMeglio, Consultant, USA

Module 11: Quality Assurance
L.11.1: Quality Assurance
A. Francis DiMeglio, Consultant, USA


Module 12: Industry Presentations

L.12.1: General Electric Presentation
Raul Pomares, General Electric Company, USA
Presentation not available electronically. Please contact presenter.

L.12.2: Rust Federal Services Northwest Presentation
John McCoy, Rust Federal Services Northwest, USA
Presentation not available electronically. Please contact presenter.

L.12.3a: Transnucleaire Presentation (Viewgraphs and Paper)
Daniele Raisonnier, Transnucleaire, France

L.12.3b: Nuclear Cargo + Services Presentation
Thomas Schmidt, Nuclear Cargo + Services
Presentation not available electronically. Please contact presenter.

L.12.4: Edlow International Presentation
Norman Ravenscroft, Edlow International Company
Presentation not available electronically. Please contact presenter.

L.12.5: NAC International Presentation
John Patterson, NAC International
Presentation not available electronically. Please contact presenter.


Module 13: Special Lectures

L.13.1: Greek Experience with Shipment of Research Reactor Spent Fuel
Costas Papastergiou, National Cente for Scientific Research "Demokritos", Greece

L.13.2: Chilean Experience with Shipment of Research Reactor Spent Fuel
Juan Klein, Comision Chilena de Energia Nuclear - La Reina, Chile

L.13.3: Shipment of Spent Fuel of the FRG-1 Research Reactor
Wilfried Krull, Forschungszentrum Geesthacht - GKSS, Germany

L.13.3a: Supplement to L.13.3, "Shipment pf Spent Fuel of the FRG-1 Research Reactor"
Wilfried Krull, Forschungszentrum Geesthacht - GKSS, Germany
Presentation not available electronically. Please contact presenter.

L.13.4: Japanese Experience with Shipment of Research Reactor Spent Fuel
Fusao Nakayama, Japan Atomic Energy Research Institute, Japan

L.13.5: Experience on Wet Storage Spent Fuel Sipping at IAE-R1 Brazilian Research Reactor Roberto Frajndlich, Instituto de Pesquisas Energeticas e Nucleares (IPEN), Brazil

L.13.6: The Problems of Treatment of Irradiated Fuel at Russian Research Reactors
Nikolai Arkhangelsky, Ministry of Atomic Energy, Russia

L.13.6a: Russian Federation Federal Law on the Use of Atomic Energy

L.13.7: Australian Experience with Dry Storage of Research Reactor Spent Fuel
Allan Murray, Embassy of Australia, Washington, DC

L.13.8: Swedish Experience with Shipment of MTR Spent Fuel
Erik Jonsson, Studsvik Nuclear AB, Sweden

L.13.9: Case Study: September 1996 Shipment from Chile and Columbia to SRS
Keith Brown, Science Applications International Company, USA

L.13.10: Australian Experience with Shipment of Research Reactor Spent Fuel
Allan Murray, Embassy of Australia, Washington, DC

L.13.10a ANSTO Public Environment Report, "Transport of HIFAR Spent Fuel from Lucas Heights Research Establishment to the United Kingdom for Reprocessing
Australian Nuclear Science and Technology Organisation (ANSTO)
Document not currently available electronically. Please contact author.

L.13.11: Final Storage of MTR Fuel in Deep Rock Repository
Erik Jonsson, Studsvik Nuclear AB, Sweden

L.13.12: Improved Communication with Electronic Mail
William Woodruff, Argonne National Laboratory, USA