B. M. Mweetwa, E. Ampomah-Amoako, E. Akaho, C. Odoi
{"title":"用蒙特卡罗粒子（MCNP）程序预测加纳研究堆1（GHARR-1）运行19年后的电子和动力学参数","authors":"B. M. Mweetwa, E. Ampomah-Amoako, E. Akaho, C. Odoi","doi":"10.4236/wjnst.2018.84014","DOIUrl":null,"url":null,"abstract":"The Ghana Research Reactor-1 (GHARR-1) core was modified with an addition of a 9.0 mm layer of beryllium to the top shim tray to compensate for reactivity loss due to fuel depletion after 19 years of operation. Neutronic and kinetic parameters have been predicted using Monte Carlo N-Particle Code version 5 (MCNP5) to determine whether they were within acceptable operating margins. Excess reactivity, control rod worth, moderator reactivity coefficient, delayed neutron fraction and neutron generation time have been predicted as 3.86, 6.98, −0.1218 mk/°C, 8.17507 × 10−3 Δk/k, and 8.147 × 10−5 s respectively. These parameters compared favorably with those provided in the initial Safety Analysis Report.","PeriodicalId":61566,"journal":{"name":"核科学与技术国际期刊(英文)","volume":null,"pages":null},"PeriodicalIF":0.0000,"publicationDate":"2018-09-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"1","resultStr":"{\"title\":\"Prediction of Neutronic and Kinetic Parameters of Ghana Research Reactor 1 (GHARR-1) after 19 Years of Operation Using Monte Carlo-N Particle (MCNP) Code\",\"authors\":\"B. M. Mweetwa, E. Ampomah-Amoako, E. Akaho, C. Odoi\",\"doi\":\"10.4236/wjnst.2018.84014\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"The Ghana Research Reactor-1 (GHARR-1) core was modified with an addition of a 9.0 mm layer of beryllium to the top shim tray to compensate for reactivity loss due to fuel depletion after 19 years of operation. Neutronic and kinetic parameters have been predicted using Monte Carlo N-Particle Code version 5 (MCNP5) to determine whether they were within acceptable operating margins. Excess reactivity, control rod worth, moderator reactivity coefficient, delayed neutron fraction and neutron generation time have been predicted as 3.86, 6.98, −0.1218 mk/°C, 8.17507 × 10−3 Δk/k, and 8.147 × 10−5 s respectively. These parameters compared favorably with those provided in the initial Safety Analysis Report.\",\"PeriodicalId\":61566,\"journal\":{\"name\":\"核科学与技术国际期刊(英文)\",\"volume\":null,\"pages\":null},\"PeriodicalIF\":0.0000,\"publicationDate\":\"2018-09-26\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"1\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"核科学与技术国际期刊(英文)\",\"FirstCategoryId\":\"1087\",\"ListUrlMain\":\"https://doi.org/10.4236/wjnst.2018.84014\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"\",\"JCRName\":\"\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"核科学与技术国际期刊(英文)","FirstCategoryId":"1087","ListUrlMain":"https://doi.org/10.4236/wjnst.2018.84014","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
Prediction of Neutronic and Kinetic Parameters of Ghana Research Reactor 1 (GHARR-1) after 19 Years of Operation Using Monte Carlo-N Particle (MCNP) Code
The Ghana Research Reactor-1 (GHARR-1) core was modified with an addition of a 9.0 mm layer of beryllium to the top shim tray to compensate for reactivity loss due to fuel depletion after 19 years of operation. Neutronic and kinetic parameters have been predicted using Monte Carlo N-Particle Code version 5 (MCNP5) to determine whether they were within acceptable operating margins. Excess reactivity, control rod worth, moderator reactivity coefficient, delayed neutron fraction and neutron generation time have been predicted as 3.86, 6.98, −0.1218 mk/°C, 8.17507 × 10−3 Δk/k, and 8.147 × 10−5 s respectively. These parameters compared favorably with those provided in the initial Safety Analysis Report.
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