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Title: Operating margin of Soviet RBMK-1000 nuclear power reactors

This paper reports on a coupled thermal- hydraulic analysis that is performed for the Soviet-designed RBMK-1000 nuclear power reactor to assess the operating margin to critical heat flux (CHF); the Chernobyl-4 reactor serves as the principal model for this study. Calculations are performed using a simplified subchannel analysis. The overall analysis involves an iterative search to determine the individual subchannel flow rates, and a boiling transition analysis is performed to obtain a measure of the core operating margin. The operating margin is determined via two distinct methods. The first involves a calculation of the core critical power ratio (CPR) using an empirically derived correlation that the Soviets developed expressly for the RBMK-1000. Additionally, various subchannel CHF correlations typical of those used in the design of nuclear-powered reactors in the United States are also employed. When the Soviet critical power correlation is used, the calculations carried out for both normal operating and reference overpower conditions result in CPRs of 1.115 and 1.019, respectively. In most cases, the subchannel CHF correlations indicate that additional operating margin over that calculated by the Soviet critical power correlation exists for this design.
Authors:
;  [1] ;  [2]
  1. (Pennsylvania State Univ., University Park, PA (United States). Dept. of Nuclear Engineering)
  2. (Westinghouse Electric Corp., Pittsburgh, PA (United States))
Publication Date:
OSTI Identifier:
5420200
Resource Type:
Journal Article
Resource Relation:
Journal Name: Nuclear Technology; (United States); Journal Volume: 96:3
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CHERNOBYLSK-4 REACTOR; HEAT FLUX; ITERATIVE METHODS; NUCLEAR POWER PLANTS; OPERATION; REACTOR CORES; USSR; ASIA; DEVELOPED COUNTRIES; ENRICHED URANIUM REACTORS; EUROPE; GRAPHITE MODERATED REACTORS; LWGR TYPE REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS 210500* -- Power Reactors, Breeding