使用快速多物理场模型对 USNC 塔架进行瞬态模拟

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

Annals of Nuclear Energy Pub Date : 2025-03-22 DOI:10.1016/j.anucene.2025.111367

Zane G. Tucker , Todd S. Palmer

{"title":"使用快速多物理场模型对 USNC 塔架进行瞬态模拟","authors":"Zane G. Tucker , Todd S. Palmer","doi":"10.1016/j.anucene.2025.111367","DOIUrl":null,"url":null,"abstract":"<div><div>A multiphysics model of the Pylon microreactor, currently under development by Ultra Safe Nuclear Corporation, has been designed and implemented for the purpose of later constructing and testing an autonomous control system. This model is implemented in a custom simulation program written in Fortran 2003, which uses a Runge–Kutta integrator to solve the necessary differential equations. Representative “modules” have been constructed for the reactor physics, Brayton cycle turbogenerator, and radiative ultimate heat sink in a replaceable manner. This work describes the governing equations of this model, the assumptions that lead to these equations, and software validation efforts. Simulations of two representative power-changing transients are described and analyzed.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111367"},"PeriodicalIF":1.9000,"publicationDate":"2025-03-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Transient simulation of the USNC Pylon using a rapid multiphysics model\",\"authors\":\"Zane G. Tucker , Todd S. Palmer\",\"doi\":\"10.1016/j.anucene.2025.111367\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>A multiphysics model of the Pylon microreactor, currently under development by Ultra Safe Nuclear Corporation, has been designed and implemented for the purpose of later constructing and testing an autonomous control system. This model is implemented in a custom simulation program written in Fortran 2003, which uses a Runge–Kutta integrator to solve the necessary differential equations. Representative “modules” have been constructed for the reactor physics, Brayton cycle turbogenerator, and radiative ultimate heat sink in a replaceable manner. This work describes the governing equations of this model, the assumptions that lead to these equations, and software validation efforts. Simulations of two representative power-changing transients are described and analyzed.</div></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":\"218 \",\"pages\":\"Article 111367\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2025-03-22\",\"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/S0306454925001847\",\"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/S0306454925001847","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

本文章由计算机程序翻译，如有差异，请以英文原文为准。

查看原文本刊更多论文

Transient simulation of the USNC Pylon using a rapid multiphysics model

A multiphysics model of the Pylon microreactor, currently under development by Ultra Safe Nuclear Corporation, has been designed and implemented for the purpose of later constructing and testing an autonomous control system. This model is implemented in a custom simulation program written in Fortran 2003, which uses a Runge–Kutta integrator to solve the necessary differential equations. Representative “modules” have been constructed for the reactor physics, Brayton cycle turbogenerator, and radiative ultimate heat sink in a replaceable manner. This work describes the governing equations of this model, the assumptions that lead to these equations, and software validation efforts. Simulations of two representative power-changing transients are described and analyzed.

求助全文

通过发布文献求助，成功后即可免费获取论文全文。去求助

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.