Fully integrated analysis of reactor kinetics, thermalhydraulics and the reactor control system in the MAPLE-X10 research reactor
Creators
- 1. Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Nuclear Research Establishment
Description
A prototype research reactor, designated MAPLE-X10 (Multipurpose Applied Physics Lattice Experimental - X 10MW), is currently being built at AECL's Chalk River Laboratories. The CATHENA (Canadian Algorithm for Thermalhydraulic Network Analysis) two-fluid code was used in the safety analysis of the reactor to determine the adequacy of core cooling during postulated reactivity and loss-of-forced-flow transients. The system responses to a postulated transient are predicted including the feedback between reactor kinetics, thermalhydrauilcs and the reactor control systems. This paper describes the MAPLE-X10 reactor and the modelling methodology used. Sample simulations of postulated loss-of-heat-sink and loss-of-regulation transients are presented. (author)
Files
23087467.pdf
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the third Asian symposium on research reactor
- Imprint Pagination
- 694 p.
- Journal Page Range
- p. 205-214.
- Report number
- JAERI-M--92-028
Conference
- Title
- 3. Asian symposium on research reactor.
- Dates
- 11-14 Nov 1991.
- Place
- Hitachi, Ibaraki (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 23087467
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; HYDRODYNAMICS; MAPLE TYPE REACTORS; REACTOR CONTROL SYSTEMS; REACTOR KINETICS; RELIABILITY; SAFETY ANALYSIS; SIMULATION; THERMODYNAMICS; TRANSIENTS
- Descriptors DEC
- COMPUTER CODES; CONTROL SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HEAVY WATER MODERATED REACTORS; KINETICS; MECHANICS; REACTORS; RESEARCH AND TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS