Review and evaluation of available critical experiment data for HTGR non-proliferation fuel cycles
Description
As part of the overall effort to resolve the issues of nuclear materials diversion and weapons proliferation, General Atomic (GA) has undertaken a study on the effective utilization on low enrichment uranium (LEU) fuel cycles in the High Temperature Gas-Cooled Reactor (HTGR). In the area of the core design, this work involved a thorough evaluation of the feasibility of various possible LEU fuel cycles including a definition of potential problems. Among the items considered in this core study were calculational methods for LEU fuel in HTGRs. In this regard, a review was undertaken of the available experimental data from critical facilities using LEU in HTGR or HTGR-like assemblies, which could be used to validate the physics design codes used at GA for the non-proliferation design work. The results of this review are summarized
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.
Files
Additional details
Publishing Information
- Imprint Pagination
- 38 p.
- Report number
- GA-A--14593
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 9389967
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; CONFIGURATION; CRITICALITY; FEASIBILITY STUDIES; FUEL ASSEMBLIES; FUEL CYCLE; HTGR TYPE REACTORS; ISOTOPE SEPARATION; MATHEMATICAL MODELS; REACTOR CORES; ZERO POWER REACTORS
- Descriptors DEC
- EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SEPARATION PROCESSES