CERCA LEU fuel assemblies testing in Maria Reactor - safety analysis summary and testing program scope.
Conference
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OSTI ID:979003
The presented paper contains neutronic and thermal-hydraulic (for steady and unsteady states) calculation results prepared to support annex to Safety Analysis Report for MARIA reactor in order to obtain approval for program of testing low-enriched uranium (LEU) lead test fuel assemblies (LTFA) manufactured by CERCA. This includes presentation of the limits and operational constraints to be in effect during the fuel testing investigations. Also, the scope of testing program (which began in August 2009), including additional measurements and monitoring procedures, is described.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA)
- DOE Contract Number:
- DE-AC02-06CH11357
- OSTI ID:
- 979003
- Report Number(s):
- ANL/NE/CP-66930; TRN: US1003063
- Resource Relation:
- Conference: 31st International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR 2009); Nov. 1, 2009 - Nov. 5, 2009; Beijing, China
- Country of Publication:
- United States
- Language:
- ENGLISH
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