{"title":"BTRR model development and verification for Monte Carlo simulation","authors":"Saad Islam , Mohammad Abdul Motalab","doi":"10.1016/j.anucene.2025.111419","DOIUrl":null,"url":null,"abstract":"<div><div>The Bangladesh Atomic Energy Commission’s TRIGA Mark II research reactor (BTRR), located near Dhaka, has been operational since September 1986, primarily for training, education, radioisotope production, and research. Currently, the Reactor Physics and Engineering Division is enhancing its analysis methods by employing modern tools like high-fidelity Monte Carlo analysis and introducing advanced codes and cross-section libraries. This study details the new reactor model implemented by means of the OpenMC code using the nuclear cross-section data libraries based on the ENDF/B-VIII.0 and ENDF/B-VII.1, focusing on calculating critical reactor parameters such as core excess reactivity, shutdown margin, control rod worth, power peaking factors, etc. The accuracy of the model verified by comparisons with previous calculations and experimental data showed good agreement.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111419"},"PeriodicalIF":1.9000,"publicationDate":"2025-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454925002361","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
The Bangladesh Atomic Energy Commission’s TRIGA Mark II research reactor (BTRR), located near Dhaka, has been operational since September 1986, primarily for training, education, radioisotope production, and research. Currently, the Reactor Physics and Engineering Division is enhancing its analysis methods by employing modern tools like high-fidelity Monte Carlo analysis and introducing advanced codes and cross-section libraries. This study details the new reactor model implemented by means of the OpenMC code using the nuclear cross-section data libraries based on the ENDF/B-VIII.0 and ENDF/B-VII.1, focusing on calculating critical reactor parameters such as core excess reactivity, shutdown margin, control rod worth, power peaking factors, etc. The accuracy of the model verified by comparisons with previous calculations and experimental data showed good agreement.
期刊介绍:
Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.