Published March 1992 | Version v1
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Fully integrated analysis of reactor kinetics, thermalhydraulics and the reactor control system in the MAPLE-X10 research reactor

  • 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)

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Part of:
Proceedings of the third Asian symposium on research reactor

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).

Optional Information