NUREG/IA-0175, Analysis of Pin-by-Effects for LWR Rod Ejection Accident
نویسندگان
چکیده
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, bumup 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.
منابع مشابه
NUREG/IA-0215 "Spatial Effects and Uncertainty Analysis for Rod Ejection Accidents in a PWR."
DISCLAIMER: This report was prepared under an international cooperative agreement for the exchange of technical information. Neither the U.S. Government nor any agency thereof, nor any employee, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, of any information, apparatus, product or process disclo...
متن کاملNUREG/IA-0477, "International Agreement Report - Thermal Hydraulic and Fuel Rod Mechanical Combination Analysis of Kuosheng Nuclear Power Plant with RELAP5 MOD3.3/FRAPTRAN/Python in SNAP Interface."
.............................................................................................................................. iii FOREWORD ............................................................................................................................. V LIST OF FIGURES ....................................................................................................................
متن کاملPwr Control Rod Ejection Analysis with the Moc Code Decart
During the past several years, a comprehensive high fidelity reactor core modeling capability has been developed called the Numerical Nuclear Reactor (NNR) for detailed analysis of Light Water Reactors. The project was initially sponsored as part of a US-ROK collaborative DOE I-NERI project and the past two years has been sponsored by EPRI to address specific fuel performance issues as part of ...
متن کاملNUREG/IA-0407, "Proposal for the Development and Implementation of an Uncertainty and Sensitivity Analysis Module in SNAP."
متن کامل
i POWER LEVEL EFFECT IN A PWR ROD EJECTION ACCIDENT
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 neu...
متن کامل