Development of high-fidelity neutronics/thermal-hydraulics coupling system for the hexagonal reactor cores based on NECP-X/CTF

Shuaizheng Li; Zhouyu Liu; Junji Chen; Minwan Zhang; Liangzhi Cao; Hongchun Wu

doi:10.1016/j.anucene.2023.109822

Development of high-fidelity neutronics/thermal-hydraulics coupling system for the hexagonal reactor cores based on NECP-X/CTF

Shuaizheng Li
, Zhouyu Liu
, Junji Chen
, Minwan Zhang
, Liangzhi Cao
, Hongchun Wu

School of Energy and Power Engineering

Research output: Contribution to journal › Review article › peer-review

3 Scopus citations

Abstract

There are some high-fidelity neutronics/thermal-hydraulics (N-TH) coupling systems for the commercial rectangular PWRs. A new high-fidelity N-TH coupling approach for the hexagonal core is introduced in this work. The rod-centered channel division is applied, and the input card for the subchannel code CTF, which considers parallel calculation, is automatically generated. The mesh mapping relationship is established between the neutronics code NECP-X and CTF simultaneously. The coupling system is applied to the VVER-1000 reactor, and the difference between the closed-channel codes and subchannel codes is analyzed. The results agree well with reference values and the bias between the closed-channel and subchannel codes is acceptable.

Original language	English
Article number	109822
Journal	Annals of Nuclear Energy
Volume	188
DOIs	https://doi.org/10.1016/j.anucene.2023.109822
State	Published - Aug 2023

Keywords

CTF
Hexagonal core
NECP-X
Neutronics and thermal-hydraulic coupling

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10.1016/j.anucene.2023.109822

Cite this

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title = "Development of high-fidelity neutronics/thermal-hydraulics coupling system for the hexagonal reactor cores based on NECP-X/CTF",

abstract = "There are some high-fidelity neutronics/thermal-hydraulics (N-TH) coupling systems for the commercial rectangular PWRs. A new high-fidelity N-TH coupling approach for the hexagonal core is introduced in this work. The rod-centered channel division is applied, and the input card for the subchannel code CTF, which considers parallel calculation, is automatically generated. The mesh mapping relationship is established between the neutronics code NECP-X and CTF simultaneously. The coupling system is applied to the VVER-1000 reactor, and the difference between the closed-channel codes and subchannel codes is analyzed. The results agree well with reference values and the bias between the closed-channel and subchannel codes is acceptable.",

keywords = "CTF, Hexagonal core, NECP-X, Neutronics and thermal-hydraulic coupling",

author = "Shuaizheng Li and Zhouyu Liu and Junji Chen and Minwan Zhang and Liangzhi Cao and Hongchun Wu",

note = "Publisher Copyright: {\textcopyright} 2023 Elsevier Ltd",

year = "2023",

month = aug,

doi = "10.1016/j.anucene.2023.109822",

language = "英语",

volume = "188",

journal = "Annals of Nuclear Energy",

issn = "0306-4549",

publisher = "Elsevier Ltd",

}

TY - JOUR

T1 - Development of high-fidelity neutronics/thermal-hydraulics coupling system for the hexagonal reactor cores based on NECP-X/CTF

AU - Li, Shuaizheng

AU - Liu, Zhouyu

AU - Chen, Junji

AU - Zhang, Minwan

AU - Cao, Liangzhi

AU - Wu, Hongchun

PY - 2023/8

Y1 - 2023/8

N2 - There are some high-fidelity neutronics/thermal-hydraulics (N-TH) coupling systems for the commercial rectangular PWRs. A new high-fidelity N-TH coupling approach for the hexagonal core is introduced in this work. The rod-centered channel division is applied, and the input card for the subchannel code CTF, which considers parallel calculation, is automatically generated. The mesh mapping relationship is established between the neutronics code NECP-X and CTF simultaneously. The coupling system is applied to the VVER-1000 reactor, and the difference between the closed-channel codes and subchannel codes is analyzed. The results agree well with reference values and the bias between the closed-channel and subchannel codes is acceptable.

AB - There are some high-fidelity neutronics/thermal-hydraulics (N-TH) coupling systems for the commercial rectangular PWRs. A new high-fidelity N-TH coupling approach for the hexagonal core is introduced in this work. The rod-centered channel division is applied, and the input card for the subchannel code CTF, which considers parallel calculation, is automatically generated. The mesh mapping relationship is established between the neutronics code NECP-X and CTF simultaneously. The coupling system is applied to the VVER-1000 reactor, and the difference between the closed-channel codes and subchannel codes is analyzed. The results agree well with reference values and the bias between the closed-channel and subchannel codes is acceptable.

KW - CTF

KW - Hexagonal core

KW - NECP-X

KW - Neutronics and thermal-hydraulic coupling

UR - https://www.scopus.com/pages/publications/85151810372

U2 - 10.1016/j.anucene.2023.109822

DO - 10.1016/j.anucene.2023.109822

M3 - 文献综述

AN - SCOPUS:85151810372

SN - 0306-4549

VL - 188

JO - Annals of Nuclear Energy

JF - Annals of Nuclear Energy

M1 - 109822

ER -

Development of high-fidelity neutronics/thermal-hydraulics coupling system for the hexagonal reactor cores based on NECP-X/CTF

Abstract

Keywords

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