{"title":"基于模型模型的异构泄漏模型","authors":"S. Santandrea , L. Graziano","doi":"10.1016/j.anucene.2025.111449","DOIUrl":null,"url":null,"abstract":"<div><div>This paper presents some developments of the APOLLO3<span><math><msup><mrow></mrow><mrow><mtext>®</mtext></mrow></msup></math></span>code and their applications in support to industrial studies. We describe a numerical technique to implement, in the framework of the Method Of Characteristics (MOC), the Heterogeneous Leakage Model (HLM). We preliminarily set up the theoretical framework of this model and clarify some aspects related to its use as homogenization technique that we believe important. In fact in the classic use of HLM for homogenization some important approximations are made to switch from complex-valued fluxes to real-valued weighting functions. We suggest an approach to avoid such approximations in practice. Then we describe a new numerical technique to solve with the MOC the HLM. The approach consists in integrating the complex-valued leakage term of the HLM directly in the cross section, and therefore to generalize MOC by integrating a complex-valued function. Moreover we detail also the necessary modifications that are necessary to adapt the classical algorithm of critical search (valid for the classical <span><math><mrow><mi>D</mi><msup><mrow><mi>B</mi></mrow><mrow><mn>2</mn></mrow></msup></mrow></math></span> leakage model) to the new context. Numerical results are shown in support to these developments.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"220 ","pages":"Article 111449"},"PeriodicalIF":1.9000,"publicationDate":"2025-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"A MOC-based heterogeneous leakage model\",\"authors\":\"S. Santandrea , L. Graziano\",\"doi\":\"10.1016/j.anucene.2025.111449\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>This paper presents some developments of the APOLLO3<span><math><msup><mrow></mrow><mrow><mtext>®</mtext></mrow></msup></math></span>code and their applications in support to industrial studies. We describe a numerical technique to implement, in the framework of the Method Of Characteristics (MOC), the Heterogeneous Leakage Model (HLM). We preliminarily set up the theoretical framework of this model and clarify some aspects related to its use as homogenization technique that we believe important. In fact in the classic use of HLM for homogenization some important approximations are made to switch from complex-valued fluxes to real-valued weighting functions. We suggest an approach to avoid such approximations in practice. Then we describe a new numerical technique to solve with the MOC the HLM. The approach consists in integrating the complex-valued leakage term of the HLM directly in the cross section, and therefore to generalize MOC by integrating a complex-valued function. Moreover we detail also the necessary modifications that are necessary to adapt the classical algorithm of critical search (valid for the classical <span><math><mrow><mi>D</mi><msup><mrow><mi>B</mi></mrow><mrow><mn>2</mn></mrow></msup></mrow></math></span> leakage model) to the new context. Numerical results are shown in support to these developments.</div></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":\"220 \",\"pages\":\"Article 111449\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2025-05-01\",\"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/S030645492500266X\",\"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":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S030645492500266X","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}
This paper presents some developments of the APOLLO3code and their applications in support to industrial studies. We describe a numerical technique to implement, in the framework of the Method Of Characteristics (MOC), the Heterogeneous Leakage Model (HLM). We preliminarily set up the theoretical framework of this model and clarify some aspects related to its use as homogenization technique that we believe important. In fact in the classic use of HLM for homogenization some important approximations are made to switch from complex-valued fluxes to real-valued weighting functions. We suggest an approach to avoid such approximations in practice. Then we describe a new numerical technique to solve with the MOC the HLM. The approach consists in integrating the complex-valued leakage term of the HLM directly in the cross section, and therefore to generalize MOC by integrating a complex-valued function. Moreover we detail also the necessary modifications that are necessary to adapt the classical algorithm of critical search (valid for the classical leakage model) to the new context. Numerical results are shown in support to these developments.
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.