Activities of the OECD/NEA Expert Group on Assay Data for Spent Nuclear Fuel
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Institute for Energy Technology (IFE), Halden (Norway). OECD Halden Reactor Project
Management of spent nuclear fuel is a key issue for many NEA member countries. In nuclear criticality safety, the decision of many countries to advance burnup credit as part of their licensing strategy has heightened recent interest in experimental data needed to validate computer codes used in burnup credit calculations. This paper discusses recent activities of an Expert Group on assay data, formed under the OECD/NEA/NSC/WPNCS (Working Party on Nuclear Criticality Safety) to help coordinate isotopic assay data activities and facilitate international collaboration between NEA member countries developing or implementing burnup credit methodologies. Recent activities of the Expert Group are described, focusing on the planned expansion of the Spent Fuel Isotopic Composition Database (SFCOMPO), and preparation of a state-of-the-art report on assay data that includes sections on recommended radiochemical analysis methods, techniques, and lessons learned from previous experiments.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Institute for Energy Technology (IFE), Halden (Norway). OECD Halden Reactor Project
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1025821
- Resource Relation:
- Conference: CD Proceedings of the International Workshop on Advances in Applications of Burnup , Cordoba (Spain), 27-30 Oct 2009
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
07 ISOTOPE AND RADIATION SOURCES
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY
BURNUP
COMPUTER CODES
CRITICALITY
FOCUSING
LICENSING
MANAGEMENT
NUCLEAR FUELS
RADIOCHEMICAL ANALYSIS
SAFETY
SPENT FUELS
Nuclear Criticality Safety Program (NCSP)
Spent Nuclear Fuel Management
Burnup Credit
Isotopic Assay Data Activities Coordination
International Collaboration Facilitation
Spent Fuel Isotopic Composition Database (SFCOMPO)
Assay Data
Radiochemical Analysis Methods
Techniques
Lessons