{"title":"Benchmarking of MCBEND computer code against the PWR shield design","authors":"R. Khan, M. N. Khan, M. Qureshi","doi":"10.1109/PGSRET.2017.8251814","DOIUrl":null,"url":null,"abstract":"A Nuclear Power Plant has major concern of The main objective of this research work is to qualify the radiation shield design computer code MCBEND against the reference results of typical PWR type Chashma Nuclear Power Plant-1 (CNPP- 1). For this purpose, a detailed 3-D computational model of the radial and axial shield of CNPP-1 is developed employing Monte Carlo computer code MCBEND equipped with DICE cross section libraries. For validation purpose, this paper compares the MCBEND simulated neutron flux distribution in the reactor shield with the reference values of CNPP-1. The predicted results captures the behavior of reference values and exhibits reasonable good agreement with the reference values.","PeriodicalId":336020,"journal":{"name":"2017 3rd International Conference on Power Generation Systems and Renewable Energy Technologies (PGSRET)","volume":"2 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"2017-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"1","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"2017 3rd International Conference on Power Generation Systems and Renewable Energy Technologies (PGSRET)","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1109/PGSRET.2017.8251814","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 1
Abstract
A Nuclear Power Plant has major concern of The main objective of this research work is to qualify the radiation shield design computer code MCBEND against the reference results of typical PWR type Chashma Nuclear Power Plant-1 (CNPP- 1). For this purpose, a detailed 3-D computational model of the radial and axial shield of CNPP-1 is developed employing Monte Carlo computer code MCBEND equipped with DICE cross section libraries. For validation purpose, this paper compares the MCBEND simulated neutron flux distribution in the reactor shield with the reference values of CNPP-1. The predicted results captures the behavior of reference values and exhibits reasonable good agreement with the reference values.