{"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":2.3000,"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}
引用次数: 0
Abstract
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.
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.
京公网安备 11010802042870号
京ICP备2023020795号-1
分享
求助内容：
应助结果提醒方式：
扫码关注我们
