SciTech Connect

Title: Validation of a RELAP5 computer model for a VVER-1000 nuclear power plant

Validation of a RELAP5 computer model for a VVER-1000 nuclear power plant This paper describes a computer model that has been developed for a VVER-1000 nuclear power plant for use with the RELAP5/MOD3.1.1 computer code in the analyses of operational occurrences abnormal events, and design basis scenarios. This model will provide a significant analytical capability for the Bulgarian nuclear regulatory body (Committee on the Use of Atomic Energy For Peaceful Purposes) and the Bulgarian technical specialists located at the power plant site (Kozloduy Nuclear Power Plant). In addition, the initial validation of computer model has been completed and is described in the paper. The analytical results are compared with data obtained during planned testing at the power plant; the test performed was the trip of a single main coolant pump. In addition, the paper provides a discussion of various other RELAP5 parameters calculated for the main coolant pump trip scenario. This model development and validation analysis represents an important accomplishment in the analyses of Russian designed nuclear power plants with computer codes developed and used in Western countries. The results indicate that RELAP5 can predict the thermal-hydraulic behavior of the VVER-1000 reactor for the class of transients represented by test results. 8 refs., 11 figs., 1 tab.
Authors: ; ; ;
Publication Date:
OSTI Identifier:OSTI ID: 527884
Report Number(s):BNL--64119; CONF-970922--1
ON: DE97004060; TRN: 97:019055
DOE Contract Number:AC02-76CH00016
Resource Type:Conference
Resource Relation:Conference: NURETH-8: 8. international topical meeting on nuclear reactor thermal-hydraulics, Kyoto (Japan), 30 Sep - 4 Oct 1997; Other Information: PBD: 1997
Research Org:Brookhaven National Lab., Upton, NY (United States)
Sponsoring Org:USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)
Country of Publication:United States
Language:English
Subject: 22 NUCLEAR REACTOR TECHNOLOGY; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; WWER-5 REACTOR; PRIMARY COOLANT CIRCUITS; R CODES; LOSS OF COOLANT; PUMPS; KOZLODUY-6 REACTOR; HYDRODYNAMICS; TWO-PHASE FLOW; HEAT TRANSFER; FLOW MODELS; TRANSIENTS