Reference core design of the experimental multi-purpose very high temperature reactor
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
At the start of reference core design of the Experimental Multi-Purpose Very High Temperature Reactor (VHTR), nuclear and thermo-hydraulic characteristics were studied extensively to search for optimum values of the VHTR core parameters. Described in this report are the procedures and the results of core nuclear studies, especially concerning core nuclear characteristics in radial and axial fuel zoning. Main results are the following. (1) In radial direction uniform fuel zoning is the best. (2) In axial direction suitable fuel zoning is necessary; i.e. in blockwise zoning from core top to bottom, 8, 8, 8, 6, 4, 2 w/o enriched fuel (average 6 w/o of 6 blocks) for Mark-I, and 7, 7, 5, 5, 5, 3, 3 w/o (average 5 w/o of 7 blocks) for Mark-II. (3) There is no essential difference in fuel temperature between hollow and annular fuel rods, because of low power density of the Experimental VHTR core. (4) 85 and 73 fuel columns are proposed for Mark-I and Mark-II core respectively. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
11544608.pdf
Files
(3.3 MB)
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Additional details
Additional titles
- Subtitle (English)
- Study of core nuclear characteristics for design of the core configuration
Publishing Information
- Imprint Pagination
- 113 p.
- Report number
- JAERI-M--8519
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 11544608
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BURNUP; CONFIGURATION CONTROL; FUEL MANAGEMENT; POWER DISTRIBUTION; REACTOR CORES; REACTOR FUELING; REACTOR LATTICE PARAMETERS; REACTOR LATTICES; SPECIFICATIONS; VHTR REACTOR
- Descriptors DEC
- ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MANAGEMENT; NUCLEAR MATERIALS MANAGEMENT; POWER REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS