Published April 1992
| Version v1
Report
Safety-related benchmark calculations for MTR-type reactors with HEU, MEU and LEU fuels
- 1. Argonne National Lab., IL (United States)
Description
Results are provided for the safety-related benchmark problem with HEU, MEU, and LEU fuels. Additional results include reactivity worths and power peaking factors with partially-inserted control rods. Comparisons of calculations and measurements for selected SPERT I transients are given along with results for self-limiting transients in the HEU and LEU benchmark cores. (author). 8 refs, 19 figs, 36 tabs
Additional details
Publishing Information
- Imprint Title
- Research reactor core conversion guidebook. V. 3: Analytical verification (Appendices G and H)
- Imprint Pagination
- 368 p.
- Journal Page Range
- p. 15-64.
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--643(v.3)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 23087349
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- COMPUTER CALCULATIONS; CROSS SECTIONS; FUEL ELEMENTS; HIGHLY ENRICHED URANIUM; LOSS OF FLOW; MODERATELY ENRICHED URANIUM; MODIFICATIONS; NUMERICAL DATA; POWER COEFFICIENT; REACTIVITY INSERTIONS; REACTIVITY WORTHS; REACTOR CORES; RESEARCH REACTORS; SLIGHTLY ENRICHED URANIUM; TEMPERATURE DEPENDENCE; TRANSIENTS; VOID COEFFICIENT
- Descriptors DEC
- ACCIDENTS; ACTINIDES; DATA; ELEMENTS; ENRICHED URANIUM; INFORMATION; ISOTOPE ENRICHED MATERIALS; MATERIALS; METALS; REACTIVITY COEFFICIENTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; URANIUM