Published January 1989
| Version v1
Report
Effect of fuel burnup and cross-sections on modular HTGR reactivity coefficients
Description
The temperature dependence of the reactivity coefficient in a prismatic block Modular High-Temperature Gas-Cooled Reactor (MHTGR) design is examined and found to be large and negative. Temperature coefficient results obtained with the ENDF/B-V data library were almost the same as results obtained with the earlier versions of the ENDF/B data library usually used at GA Technologies Inc. (GA) in spite of a significant eigenvalue increase with the ENDF/B-V data. The effects of fuel burnup and arbitrarily assumed cross section variations were examined and tabulated. (author). 2 refs, 7 figs, 5 tabs
Additional details
Publishing Information
- Imprint Title
- Nuclear data for the calculation of thermal reactor reactivity coefficients
- Imprint Pagination
- 132 p.
- Journal Page Range
- p. 23-31.
- Report number
- IAEA-TECDOC--491
Conference
- Title
- Advisory group on nuclear data for the calculation of thermal reactor reactivity coefficients.
- Dates
- 7-10 Dec 1987.
- Place
- Vienna (Austria).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 20064266
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; COMPUTERIZED SIMULATION; CROSS SECTIONS; HTGR TYPE REACTORS; REACTIVITY COEFFICIENTS; SENSITIVITY ANALYSIS; TEMPERATURE DEPENDENCE
- Descriptors DEC
- GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; REACTORS; SIMULATION
Optional Information
- Contract/Grant/Project number
- Contract DE-AC03-84F11963