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

页数：8

共 50 条

[41] Coarse-mesh thermal-hydraulics and neutronics coupling for the ALFRED reactor
Di Lecce, Francesco
Aufiero, Manuele
Lorenzi, Stefano
Saracco, Paolo
Alemberti, Alessandro
EUROPEAN PHYSICAL JOURNAL PLUS, 2020, 135 (02):
[42] VVER-1000 pin cell benchmark for coupled neutronics/thermal-hydraulics calculations: preliminary results
Bahdanovich, R. B.
Romanenko, V. I.
Farkhulina, A. L.
Bogdanova, E. V.
Nikonov, S. P.
Tikhomirov, G. V.
INTERNATIONAL CONFERENCE FOR YOUNG SCIENTISTS, SPECIALISTS AND POST-GRADUATES ON NUCLEAR REACTOR PHYSICS, 2018, 1133
[43] Application of a new neutronics/thermal-hydraulics coupled code for steady state analysis of light water reactors
Safavi, Amir
Esteki, Mohammad Hossein
Mirvakili, Seyed Mohammad
Arani, Mehdi Khaki
NUCLEAR ENGINEERING AND TECHNOLOGY, 2020, 52 (08) : 1603 - 1610
[44] Boron dilution transient simulation analyses in a PWR with neutronics/thermal-hydraulics coupled codes in the NURISP project
Jimenez, G.
Herrero, J. J.
Gommlich, A.
Kliem, S.
Cuervo, D.
Jimenez, J.
ANNALS OF NUCLEAR ENERGY, 2015, 84 : 86 - 97
[45] The Verification of Coupled Neutronics Thermal-Hydraulics Code NODAL3 in the PWR Rod Ejection Benchmark
Pinem, Surian
Sembiring, Tagor Malem
Liem, Peng Hong
SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2014, 2014
[46] Three-dimensional transient analysis of Xi'an pulsed reactor by the coupled neutronics and thermal-hydraulics code
Zhang, Xinyi
Jiang, Xinbiao
Zheng, Youqi
Wang, Yongping
Yin, Huabei
He, Bin
Xu, Peng
Wang, Lipeng
Guo, Hewei
Zhang, Liang
Jiang, Duoyu
Hu, Tianliang
ANNALS OF NUCLEAR ENERGY, 2022, 175
[47] An internal coupling method between neutronics and thermal-hydraulics with RMC and CTF
Li, Kaiwen
Liu, Shichang
Guo, Juanjuan
Luo, Zhen
Huang, Shanfang
Wang, Kan
ANNALS OF NUCLEAR ENERGY, 2023, 187
[48] Coarse-mesh thermal-hydraulics and neutronics coupling for the ALFRED reactor
Francesco Di Lecce
Manuele Aufiero
Stefano Lorenzi
Paolo Saracco
Alessandro Alemberti
The European Physical Journal Plus, 135
[49] Influence analysis of coupled neutronics and thermal-hydraulics on characteristics of supercritical water-cooled reactor system
Chen, Juan
Zhou, Tao
Luo, Feng
Wang, Han-Ding
Cheng, Wan-Xu
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2013, 47 (05): : 804 - 810
[50] Optimization of AHWR core design: neutronics and thermal-hydraulics analysis and calculations
Vishal Bharti
D. K. Chandraker
Arindam Chakraborty
Amit Thakur
Debasmit Sarkar
Baltej Singh
Umasankari Kannan
A. K. Nayak
S. K. Sinha
Life Cycle Reliability and Safety Engineering, 2021, 10 (1) : 71 - 80

← 1 2 3 4 5 →