{"title":"Development of Bamboo-Transient2.0 for three-dimensional PWR-core pin-by-pin Transient analysis","authors":"Junwei Qin, Yunzhao Li, Liangzhi Cao","doi":"10.1016/j.net.2025.103598","DOIUrl":null,"url":null,"abstract":"<div><div>In order to ensure the safety of the core, three-dimensional whole-core transient analysis would be carried out to obtain the pin-power distribution required by safety analysis. For this purpose, this paper presents the development of Bamboo-Transient2.0, a three-dimensional pin-by-pin transient analysis program. It adopts a fully-implicit backward finite difference method for time variable discretization, a method of exponential function expansion nodal (EFEN) SP<sub>3</sub> for spatial and angle domain neutronic calculation, and a multi-channel model for the thermal-hydraulic feedback calculation. In addition, Picard iteration is used to couple the neutronics and the thermal-hydraulics, which is intended to guarantee the convergence of coupling iteration at each time step. Moreover, the program can perform parallel computing based on Message Passing Interface (MPI) for the whole-core pin-by-pin transient analysis. Besides, a series of acceleration techniques have been applied to further reduce the computational time. The methodology and code implementation have been verified via a series of numerical tests. As demonstrated by the numerical results, the code developed in this paper shows good agreement with the reference. Furthermore, the acceleration method used in this paper enables a 141.5 times speedup in SP<sub>3</sub> neutron kinetics calculation, while the parallel efficiency maintains above 80 %. Bamboo-Transient2.0 can yield great results, whose pin-wise distributions of state parameters are reliable and thus can satisfactorily meet the requirements and purpose of safety analysis.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 8","pages":"Article 103598"},"PeriodicalIF":2.6000,"publicationDate":"2025-03-22","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/S1738573325001664","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
In order to ensure the safety of the core, three-dimensional whole-core transient analysis would be carried out to obtain the pin-power distribution required by safety analysis. For this purpose, this paper presents the development of Bamboo-Transient2.0, a three-dimensional pin-by-pin transient analysis program. It adopts a fully-implicit backward finite difference method for time variable discretization, a method of exponential function expansion nodal (EFEN) SP3 for spatial and angle domain neutronic calculation, and a multi-channel model for the thermal-hydraulic feedback calculation. In addition, Picard iteration is used to couple the neutronics and the thermal-hydraulics, which is intended to guarantee the convergence of coupling iteration at each time step. Moreover, the program can perform parallel computing based on Message Passing Interface (MPI) for the whole-core pin-by-pin transient analysis. Besides, a series of acceleration techniques have been applied to further reduce the computational time. The methodology and code implementation have been verified via a series of numerical tests. As demonstrated by the numerical results, the code developed in this paper shows good agreement with the reference. Furthermore, the acceleration method used in this paper enables a 141.5 times speedup in SP3 neutron kinetics calculation, while the parallel efficiency maintains above 80 %. Bamboo-Transient2.0 can yield great results, whose pin-wise distributions of state parameters are reliable and thus can satisfactorily meet the requirements and purpose of safety analysis.
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