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Title: POWER LEVEL EFFECT IN A PWR ROD EJECTION ACCIDENT.

Abstract

The purpose of this study is to determine the effect of the initial power level during a rod ejection accident (REA) on the ejected rod worth and the resulting energy deposition in the fuel. The model used is for the hot zero power (HZP) conditions at the end of a typical fuel cycle for the Three Mile Island Unit 1 pressurized water reactor. PARCS, a transient, three-dimensional, two-group neutron nodal diffusion code, coupled with its own thermal-hydraulics model, is used to perform both steady-state and transient simulations. The worth of an ejected control rod is affected by both power level, and the positions of control banks. As the power level is increased, the worth of a single central control rod tends to drop due to thermal-hydraulic feedback and control bank removal, both of which flatten the radial neutron flux and power distributions. Although the peak fuel pellet enthalpy rise during an REA will be greater for a given ejected rod worth at elevated initial power levels, it is more likely the HZP condition will cause a greater net energy deposition because an ejected rod will have the highest worth at HZP. Thus, the HZP condition can be considered the mostmore » conservative in a safety evaluation.« less

Authors:
; ;
Publication Date:
Research Org.:
Brookhaven National Lab., Upton, NY (US)
Sponsoring Org.:
NRC/DOE (US)
OSTI Identifier:
799476
Report Number(s):
BNL-NUREG-69285
R&D Project: JCNY6587; 26015110201; TRN: US0204442
DOE Contract Number:  
AC02-98CH10886
Resource Type:
Conference
Resource Relation:
Conference: PHYSOR 2002 INTERNATIONAL CONFERENCE ON THE NEW FRONTIERS OF NUCLEAR TECHNOLOGY, SEOUL (KR), 10/07/2002--10/10/2002; Other Information: PBD: 7 Oct 2002
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CONTROL ELEMENTS; DEPOSITION; DIFFUSION; ENTHALPY; FEEDBACK; FUEL CYCLE; FUEL PELLETS; NEUTRON FLUX; NEUTRONS; POWER DISTRIBUTION; PWR TYPE REACTORS; ROD EJECTION ACCIDENTS; SAFETY; TRANSIENTS

Citation Formats

DIAMOND, D J, BROMLEY, B P, and ARONSON, A L. POWER LEVEL EFFECT IN A PWR ROD EJECTION ACCIDENT.. United States: N. p., 2002. Web.
DIAMOND, D J, BROMLEY, B P, & ARONSON, A L. POWER LEVEL EFFECT IN A PWR ROD EJECTION ACCIDENT.. United States.
DIAMOND, D J, BROMLEY, B P, and ARONSON, A L. Mon . "POWER LEVEL EFFECT IN A PWR ROD EJECTION ACCIDENT.". United States. https://www.osti.gov/servlets/purl/799476.
@article{osti_799476,
title = {POWER LEVEL EFFECT IN A PWR ROD EJECTION ACCIDENT.},
author = {DIAMOND, D J and BROMLEY, B P and ARONSON, A L},
abstractNote = {The purpose of this study is to determine the effect of the initial power level during a rod ejection accident (REA) on the ejected rod worth and the resulting energy deposition in the fuel. The model used is for the hot zero power (HZP) conditions at the end of a typical fuel cycle for the Three Mile Island Unit 1 pressurized water reactor. PARCS, a transient, three-dimensional, two-group neutron nodal diffusion code, coupled with its own thermal-hydraulics model, is used to perform both steady-state and transient simulations. The worth of an ejected control rod is affected by both power level, and the positions of control banks. As the power level is increased, the worth of a single central control rod tends to drop due to thermal-hydraulic feedback and control bank removal, both of which flatten the radial neutron flux and power distributions. Although the peak fuel pellet enthalpy rise during an REA will be greater for a given ejected rod worth at elevated initial power levels, it is more likely the HZP condition will cause a greater net energy deposition because an ejected rod will have the highest worth at HZP. Thus, the HZP condition can be considered the most conservative in a safety evaluation.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2002},
month = {10}
}

Conference:
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