{"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":2.3000,"publicationDate":"2025-08-01","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":"2025/4/1 0:00:00","PubModel":"Epub","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.
孟加拉国原子能委员会的TRIGA Mark II研究堆（BTRR）位于达卡附近，自1986年9月以来一直在运行，主要用于培训、教育、放射性同位素生产和研究。目前，反应堆物理和工程部正在通过采用高保真蒙特卡罗分析等现代工具和引入先进的代码和截面库来增强其分析方法。本文详细介绍了利用基于ENDF/B-VIII的核截面数据库，通过OpenMC代码实现的新反应堆模型。0和ENDF/B-VII。1、重点计算堆芯超反应性、停机裕度、控制棒价值、功率峰值因子等关键反应堆参数。通过与前人计算和实验数据的比较，验证了模型的准确性。
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.
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