{"title":"具有连续能量精度的动态多群截面生成方法","authors":"Farzad Rahnema, Dingkang Zhang","doi":"10.1016/j.anucene.2025.111640","DOIUrl":null,"url":null,"abstract":"<div><div>In this paper, an on-the-fly multigroup cross section generation method is developed and implemented into the coarse mesh transport code COMET to account for the effects of spectral change and surrounding environment in reactor core calculations. The method consists of (1) a continuous energy stochastic response reaction rate generation module and (2) a deterministic multigroup cross section updating module. The first module is developed by extending the continuous energy response function generator for COMET to solve a set of local fixed-source transport problems with incident flux boundary conditions (or surface sources) and to generate a library of various response reaction rates. The second module constructs the phase space (continuous in space, angle, and energy) flux distribution in the regions of interest as a superposition of elements from the pre-computed library and then generates the multigroup cross sections on-the-fly. The method is benchmarked against the multigroup cross sections directly by continuous energy Monte Carlo in a set of stylized Very High Temperature Reactor (VHTR) single fuel block and whole core benchmark problems. Benchmark results demonstrate that the new method can achieve accuracy close (i.e., within two standard deviation of stochastic uncertainty) to that of continuous energy Monte Carlo while having on-the-fly computational speed.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"223 ","pages":"Article 111640"},"PeriodicalIF":1.9000,"publicationDate":"2025-06-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"On-The-Fly multigroup cross section generation method with continuous energy accuracy\",\"authors\":\"Farzad Rahnema, Dingkang Zhang\",\"doi\":\"10.1016/j.anucene.2025.111640\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>In this paper, an on-the-fly multigroup cross section generation method is developed and implemented into the coarse mesh transport code COMET to account for the effects of spectral change and surrounding environment in reactor core calculations. The method consists of (1) a continuous energy stochastic response reaction rate generation module and (2) a deterministic multigroup cross section updating module. The first module is developed by extending the continuous energy response function generator for COMET to solve a set of local fixed-source transport problems with incident flux boundary conditions (or surface sources) and to generate a library of various response reaction rates. The second module constructs the phase space (continuous in space, angle, and energy) flux distribution in the regions of interest as a superposition of elements from the pre-computed library and then generates the multigroup cross sections on-the-fly. The method is benchmarked against the multigroup cross sections directly by continuous energy Monte Carlo in a set of stylized Very High Temperature Reactor (VHTR) single fuel block and whole core benchmark problems. Benchmark results demonstrate that the new method can achieve accuracy close (i.e., within two standard deviation of stochastic uncertainty) to that of continuous energy Monte Carlo while having on-the-fly computational speed.</div></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":\"223 \",\"pages\":\"Article 111640\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2025-06-20\",\"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/S0306454925004578\",\"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/S0306454925004578","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}
On-The-Fly multigroup cross section generation method with continuous energy accuracy
In this paper, an on-the-fly multigroup cross section generation method is developed and implemented into the coarse mesh transport code COMET to account for the effects of spectral change and surrounding environment in reactor core calculations. The method consists of (1) a continuous energy stochastic response reaction rate generation module and (2) a deterministic multigroup cross section updating module. The first module is developed by extending the continuous energy response function generator for COMET to solve a set of local fixed-source transport problems with incident flux boundary conditions (or surface sources) and to generate a library of various response reaction rates. The second module constructs the phase space (continuous in space, angle, and energy) flux distribution in the regions of interest as a superposition of elements from the pre-computed library and then generates the multigroup cross sections on-the-fly. The method is benchmarked against the multigroup cross sections directly by continuous energy Monte Carlo in a set of stylized Very High Temperature Reactor (VHTR) single fuel block and whole core benchmark problems. Benchmark results demonstrate that the new method can achieve accuracy close (i.e., within two standard deviation of stochastic uncertainty) to that of continuous energy Monte Carlo while having on-the-fly computational speed.
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.