{"title":"ALFRED的初始验证:在Geant4上构建的用于TREAT能量沉积的蒙特卡罗代码","authors":"Paul A. Ferney, Nicolas P. Martin","doi":"10.1016/j.net.2025.103877","DOIUrl":null,"url":null,"abstract":"<div><div>Predicting the energy deposited in the specimen during an experiment in the Transient Reactor Test (TREAT) Facility is a complex problem due to the nature of the transients occurring in the reactor. In addition, the many particles contributing to energy deposition have different behavior in time and space. ALFRED, a new Geant4 based code, is developed to transport and simulate each particle generated in the core. This code is verified against OpenMC (Open Monte Carlo) on the Godiva benchmark and a simple TREAT model. Next, the energy deposition in TREAT is calculated: <span><math><mrow><mn>181</mn><mo>.</mo><mn>05</mn><mo>±</mo><mn>0</mn><mo>.</mo><mn>01</mn><mspace></mspace><mtext>MeV</mtext></mrow></math></span> for the “instantaneous” energy deposition (which accounts for the energy deposited within 1 s after neutron emission) in fuel and <span><math><mrow><mn>189</mn><mo>.</mo><mn>90</mn><mo>±</mo><mn>0</mn><mo>.</mo><mn>01</mn><mspace></mspace><mtext>MeV</mtext></mrow></math></span> for the total energy deposition in fuel. We discuss these results in this paper with previous calculations and experimental evaluations. This work demonstrates ALFRED’s potential as a high-fidelity tool for computing the spatial and temporal energy deposition in TREAT paving the way for a better understanding of the energy coupling factors in TREAT.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 2","pages":"Article 103877"},"PeriodicalIF":2.6000,"publicationDate":"2025-09-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Initial validation of ALFRED: A Monte Carlo code built on Geant4 for TREAT energy deposition\",\"authors\":\"Paul A. Ferney, Nicolas P. Martin\",\"doi\":\"10.1016/j.net.2025.103877\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Predicting the energy deposited in the specimen during an experiment in the Transient Reactor Test (TREAT) Facility is a complex problem due to the nature of the transients occurring in the reactor. In addition, the many particles contributing to energy deposition have different behavior in time and space. ALFRED, a new Geant4 based code, is developed to transport and simulate each particle generated in the core. This code is verified against OpenMC (Open Monte Carlo) on the Godiva benchmark and a simple TREAT model. Next, the energy deposition in TREAT is calculated: <span><math><mrow><mn>181</mn><mo>.</mo><mn>05</mn><mo>±</mo><mn>0</mn><mo>.</mo><mn>01</mn><mspace></mspace><mtext>MeV</mtext></mrow></math></span> for the “instantaneous” energy deposition (which accounts for the energy deposited within 1 s after neutron emission) in fuel and <span><math><mrow><mn>189</mn><mo>.</mo><mn>90</mn><mo>±</mo><mn>0</mn><mo>.</mo><mn>01</mn><mspace></mspace><mtext>MeV</mtext></mrow></math></span> for the total energy deposition in fuel. We discuss these results in this paper with previous calculations and experimental evaluations. This work demonstrates ALFRED’s potential as a high-fidelity tool for computing the spatial and temporal energy deposition in TREAT paving the way for a better understanding of the energy coupling factors in TREAT.</div></div>\",\"PeriodicalId\":19272,\"journal\":{\"name\":\"Nuclear Engineering and Technology\",\"volume\":\"58 2\",\"pages\":\"Article 103877\"},\"PeriodicalIF\":2.6000,\"publicationDate\":\"2025-09-20\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nuclear Engineering and Technology\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S1738573325004450\",\"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}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Technology","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S1738573325004450","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
摘要
在瞬态反应堆试验(TREAT)设施中,由于反应堆中发生瞬态的性质,预测在实验期间沉积在试样中的能量是一个复杂的问题。此外,许多参与能量沉积的粒子在时间和空间上有不同的行为。ALFRED是一种新的基于Geant4的代码,用于传输和模拟核心中产生的每个粒子。该代码在Godiva基准测试和一个简单的TREAT模型上针对OpenMC (Open Monte Carlo)进行了验证。接下来,计算TREAT中的能量沉积:燃料中的“瞬时”能量沉积(即中子发射后1 s内沉积的能量)为181.05±0.01MeV,燃料中的总能量沉积为189.90±0.01MeV。本文结合以往的计算和实验评价对这些结果进行了讨论。这项工作证明了ALFRED作为计算TREAT中时空能量沉积的高保真工具的潜力,为更好地理解TREAT中的能量耦合因素铺平了道路。
Initial validation of ALFRED: A Monte Carlo code built on Geant4 for TREAT energy deposition
Predicting the energy deposited in the specimen during an experiment in the Transient Reactor Test (TREAT) Facility is a complex problem due to the nature of the transients occurring in the reactor. In addition, the many particles contributing to energy deposition have different behavior in time and space. ALFRED, a new Geant4 based code, is developed to transport and simulate each particle generated in the core. This code is verified against OpenMC (Open Monte Carlo) on the Godiva benchmark and a simple TREAT model. Next, the energy deposition in TREAT is calculated: for the “instantaneous” energy deposition (which accounts for the energy deposited within 1 s after neutron emission) in fuel and for the total energy deposition in fuel. We discuss these results in this paper with previous calculations and experimental evaluations. This work demonstrates ALFRED’s potential as a high-fidelity tool for computing the spatial and temporal energy deposition in TREAT paving the way for a better understanding of the energy coupling factors in TREAT.
期刊介绍:
Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters.
NET covers all fields for peaceful utilization of nuclear energy and radiation as follows:
1) Reactor Physics
2) Thermal Hydraulics
3) Nuclear Safety
4) Nuclear I&C
5) Nuclear Physics, Fusion, and Laser Technology
6) Nuclear Fuel Cycle and Radioactive Waste Management
7) Nuclear Fuel and Reactor Materials
8) Radiation Application
9) Radiation Protection
10) Nuclear Structural Analysis and Plant Management & Maintenance
11) Nuclear Policy, Economics, and Human Resource Development