MCNPX simulations of NE213 scintillator neutron response functions and detection efficiencies up to 1 GeV

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2025-03-17 DOI:10.1016/j.anucene.2025.111369

M. Tajik

{"title":"MCNPX simulations of NE213 scintillator neutron response functions and detection efficiencies up to 1 GeV","authors":"M. Tajik","doi":"10.1016/j.anucene.2025.111369","DOIUrl":null,"url":null,"abstract":"<div><div>This study employed the MCNPX code to simulate the neutron response functions and detection efficiencies of an NE213 scintillator for high-energy neutrons. The MCNPX code’s PTRAC card facilitated the calculation of the scintillator’s neutron response function for mono-energetic neutrons across an energy range of 15 to 1000 MeV. MCNPX accurately reproduced the measured response for neutrons below 200 MeV. However, discrepancies emerged for higher-energy neutrons (>200 MeV), particularly in regions with low light output. In these regions, the simulated values were higher than the experimental data. The calculated neutron response functions and detection efficiencies were compared using MCNPX, SCINFUL-QMD, and CECIL codes. The MCNPX simulations showed better agreement with the measured data compared to the results generated by SCINFUL-QMD and CECIL. The uncertainties associated with the detection efficiencies calculated by MCNPX were estimated to be below 8 % for neutrons in the sub-100 MeV energy region and within 15 % for the 100–600 MeV range.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"217 ","pages":"Article 111369"},"PeriodicalIF":1.9000,"publicationDate":"2025-03-17","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/S0306454925001860","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

This study employed the MCNPX code to simulate the neutron response functions and detection efficiencies of an NE213 scintillator for high-energy neutrons. The MCNPX code’s PTRAC card facilitated the calculation of the scintillator’s neutron response function for mono-energetic neutrons across an energy range of 15 to 1000 MeV. MCNPX accurately reproduced the measured response for neutrons below 200 MeV. However, discrepancies emerged for higher-energy neutrons (>200 MeV), particularly in regions with low light output. In these regions, the simulated values were higher than the experimental data. The calculated neutron response functions and detection efficiencies were compared using MCNPX, SCINFUL-QMD, and CECIL codes. The MCNPX simulations showed better agreement with the measured data compared to the results generated by SCINFUL-QMD and CECIL. The uncertainties associated with the detection efficiencies calculated by MCNPX were estimated to be below 8 % for neutrons in the sub-100 MeV energy region and within 15 % for the 100–600 MeV range.

查看原文本刊更多论文

这项研究利用 MCNPX 代码模拟了 NE213 闪烁器对高能中子的中子响应函数和探测效率。MCNPX 代码的 PTRAC 卡有助于计算闪烁器对 15 至 1000 MeV 能量范围内单能量中子的中子响应函数。MCNPX 准确地再现了 200 MeV 以下中子的测量响应。然而，高能量中子（>200 MeV）出现了差异，特别是在光输出较低的区域。在这些区域，模拟值高于实验数据。使用 MCNPX、SCINFUL-QMD 和 CECIL 代码对计算得出的中子响应函数和探测效率进行了比较。与 SCINFUL-QMD 和 CECIL 生成的结果相比，MCNPX 模拟结果与测量数据的一致性更好。据估计，MCNPX 计算出的探测效率的不确定性在 100 MeV 以下能量区域低于 8%，在 100-600 MeV 范围内则在 15%以内。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文求助全文

来源期刊

Annals of Nuclear Energy 工程技术-核科学技术

CiteScore

4.30

自引率

21.10%

发文量

632

审稿时长

7.3 months

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.