Criticality Validation for Burnup Credit Using Recycle Pu Criticals
Conference
·
· Proceedings of the International Topical Meeting on Advanced Reactors Safety
OSTI ID:471467
- TRW Environmental Safety Systems, Inc., Vienna, VA (United States)
A set of 23 additional critical experiments were analyzed to provide additional input to the criticality validation portion of spent fuel cask analysis. The results of this analyses were combined with the previously analyzed criticals to determine the upper safety limit on keff. The combined set of criticals can be used for criticality validation for burnup credit and are better suited for the range of isotopics in spent nuclear fuels. A trend observed in the analysis was that the calculated keff deviates from the criticals in the positive direction, implying that increased burnup results in increased safety margin.
- Research Organization:
- TRW Environmental Safety Systems, Inc., Vienna, VA (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC01-91RW00134
- OSTI ID:
- 471467
- Report Number(s):
- DOE/RW/00134--M97-002; CONF-970607--9; ON: DE97004216
- Conference Information:
- Journal Name: Proceedings of the International Topical Meeting on Advanced Reactors Safety
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
27BURNUPLIB
BURNUP
CRITICALITY
Fuel Pin Diameter
HIGH-LEVEL RADIOACTIVE WASTES
Mixed Oxide (MOX) Fuel
Nuclear Criticality Safety Program (NCSP)
PLUTONIUM OXIDES
PWR TYPE REACTORS
Plutonium Utilization Program (PUP)
SCALE 4.2 Code System
SPENT FUEL CASKS
SPENT FUELS
Spent Fuel Cask Analysis
Upper Safety Limit (USL)
VALIDATION
27BURNUPLIB
BURNUP
CRITICALITY
Fuel Pin Diameter
HIGH-LEVEL RADIOACTIVE WASTES
Mixed Oxide (MOX) Fuel
Nuclear Criticality Safety Program (NCSP)
PLUTONIUM OXIDES
PWR TYPE REACTORS
Plutonium Utilization Program (PUP)
SCALE 4.2 Code System
SPENT FUEL CASKS
SPENT FUELS
Spent Fuel Cask Analysis
Upper Safety Limit (USL)
VALIDATION