LOCA simulation in a VVER-1000 with MOX fuel

Journal Article · Thu Jul 01 00:00:00 EDT 1999 · Transactions of the American Nuclear Society

OSTI ID:20005801

Carbajo, J J; Yoder, G L; Pointer, D; Ivanov, V

A wide range of thermal-hydraulic transients has been modeled with the RELAP5/MOD3.2 code for the Balakova-4 plant, a VVER-1000 V320 plant located in Russia. The detailed RELAP5 model has been prepared by the Kurchatov Institute of Moscow, Russia, and modified at Oak Ridge National Laboratory. This paper presents RELAP5 results of a large loss-of-coolant accident (LOCA) that have been compared with Russian calculated results for the same transient. The VVER-1000 core contains one lead test assembly (LTA) with mixed-oxide (MOX) fuel. The purpose of this work is to support licensing this plant to burn MOX fuel.

• Research Organization: Oak Ridge National Lab., TN (US)
• OSTI ID: 20005801
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 81; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
COMPARATIVE EVALUATIONS
LOSS OF COOLANT
MIXED OXIDE FUELS
R CODES
REACTOR LICENSING
WWER-5 REACTOR