Development of coupled neutronics/thermal-hydraulics test case for HPLWR

被引：2
|
作者：
Pham, P. [1 ]
Gamtsemlidze, I. D. [1 ]
Bandanovich, R. B. [1 ]
Nikonov, S. P. [1 ]
Smirnov, A. D. [1 ]
机构：
[1] Natl Nucl Res Univ MEPhI, Moscow Engn Phys Inst, Dept Theoret & Expt Phys Nucl Reactors, Kashirskoe Shosse 31, Moscow 115409, Russia
来源：
INTERNATIONAL CONFERENCE FOR YOUNG SCIENTISTS, SPECIALISTS, AND POSTGRADUATES ON NUCLEAR REACTOR PHYSICS 2016 (ICNRP-2016) | 2017年 / 781卷
关键词：
REACTOR; DESIGN;
D O I：
10.1088/1742-6596/781/1/012026
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
The High-Performance Light Water Reactor (HPLWR) is the European concept of a supercritical water reactor (SCWR) which is one of the most promising and innovative designs of the Generation IV nuclear reactor concepts. The thermal-hydraulics behavior of supercritical water is significantly different from water at sub-critical pressure because of the difference in the specific heat value. Coupled analysis of HPLWR assembly neutronics and thermal-hydraulics has become important because of the strong influence of the water density on the neutron spectrum and power distribution. Programs MCU (Monte-Carlo Universal) and ATHLET (Analysis of Thermal-hydraulics of Leaks and Transients) were used for better estimation of power and temperature distribution in HPLWR assembly.
引用
收藏
页数：8
相关论文
共 50 条
  • [21] A tightly coupled scheme for neutronics and thermal-hydraulics using open-source software
    Wu, Hsingtzu
    Rizwan-uddin
    ANNALS OF NUCLEAR ENERGY, 2016, 87 : 16 - 22
  • [22] Research on Neutronics/Thermal-hydraulics Coupling Effect of CFETR Blanket
    Dai T.
    Cao L.
    He Q.
    Wu H.
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2022, 56 (01): : 136 - 145
  • [23] Multi-physics analysis of SBLOCA by coupled Neutronics/ Thermal-Hydraulics full plant model
    Dizaji, Davod Naghavi
    Ghafari, Mohsen
    Vosoughi, Naser
    NUCLEAR ENGINEERING AND DESIGN, 2024, 424
  • [24] Coupled neutronics thermal-hydraulics analysis using Monte Carlo and sub-channel codes
    Vazquez, Miriam
    Tsige-Tamirat, Haileyesus
    Ammirabile, Luca
    Martin-Fuertes, Francisco
    NUCLEAR ENGINEERING AND DESIGN, 2012, 250 : 403 - 411
  • [25] Coupled Three-Dimensional Neutronics and Thermal-Hydraulics Analysis for SCWR Core Typical Transients
    Wang Lianjie
    Lu Di
    Zhao Wenbo
    JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2019, 5 (01):
  • [26] Preliminary conceptual design with neutronics and thermal-hydraulics assessments of FuSTAR
    Zhou, Xingguang
    Zhang, Dalin
    Li, Xinyu
    Lv, Xindi
    Jiang, Dianqiang
    Tian, Wenxi
    Qiu, Suizheng
    ANNALS OF NUCLEAR ENERGY, 2024, 197
  • [27] Coupled fine-mesh neutronics and thermal-hydraulics - Modeling and implementation for PWR fuel assemblies
    Jareteg, Klas
    Vinai, Paolo
    Sasic, Srdjan
    Demaziere, Christophe
    ANNALS OF NUCLEAR ENERGY, 2015, 84 : 244 - 257
  • [28] Multiphysics Modeling and Validation of Spent Fuel Isotopics Using Coupled Neutronics/Thermal-Hydraulics Simulations
    Price, Dean
    Radaideh, Majdi I.
    Mui, Travis
    Katare, Mihir
    Kozlowski, Tomasz
    SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2020, 2020
  • [29] Coupled Three Dimensional Neutronics/Thermal-hydraulics Code STTA for SCWR Core Transient Analysis
    Wang, Lianjie
    Zhao, Wenbo
    Yang, Ping
    Chen, Bingde
    Yao, Dong
    PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 3, 2014,
  • [30] RCCA EJECTION ACCIDENT ANALYSIS BASED ON COUPLED 3D NEUTRONICS AND THERMAL-HYDRAULICS
    Zang Liye
    PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 6, ICONE31 2024, 2024,
12345