Analysis of Pin-by-Pin Effects for LWR Rod Ejection Accident (NUREG/IA–0175, NSI RRC KI90–12/1–3-00, IPSN/00–13)
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Date Published: March 2000
A. Avvakumov, V. Malofeev, V. Sidorov
Nuclear Safety Institute
Russian Research Centre
Kurchatov Square 1
U.S. Nuclear Regulatory Commission, Institute for Protection and Nuclear Safety (France),
and Ministry of Science and Technologies of the Russian Federation
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
This study was undertaken to demonstrate capabilities of the pin-by-pin model used by the BARS code and to understand various effects of intra-assembly pin-by-pin representation of fuel power, burnup and temperature in calculational analysis of light water reactor rod ejection accidents (LWR REAs). Effects of pin-by-pin fuel power and bumup representation were investigated on the basis of calculations for the peripheral control rod ejection in VVER-1000 of the South Ukrainian NPP Unit 1. Comparative analysis of the REA in pressurized water reactor (PWR) of Three Mile Island Unit 1 using the BARS code with the diffusion nodal codes PARCS and CRONOS2 was done. The important differences in obtained results and effects of pin-by-pin fuel temperature representation are discussed in the report.