SPERT III E-Core critical experiment benchmarks calculation with NECP-X and KENO-VI

Chen Zhao; Zhouyu Liu; Lu Cao; Qicang Shen; Thomas Downar; Liangzhi Cao

doi:10.1016/j.pnucene.2020.103322

SPERT III E-Core critical experiment benchmarks calculation with NECP-X and KENO-VI

Chen Zhao
, Zhouyu Liu
, Lu Cao
, Qicang Shen
, Thomas Downar
, Liangzhi Cao

School of Energy and Power Engineering

Nuclear Power Institute of China
Xi'an Jiaotong University
University of Michigan, Ann Arbor

Research output: Contribution to journal › Article › peer-review

3 Scopus citations

Abstract

The Special Power Excursion Reactor Test (SPERT) III E-Core is a small experimental reactor towards experimental and theoretical investigations of kinetic and safety behavior of nuclear reactors. The SPERT III E-core model was established with a high-fidelity direct whole-core transport code NECP-X and a Monte Carlo code KENO-VI. Most of components of the reactor core were explicitly modeled in these two codes. A series of steady-state cases were calculated, ranging from 2D lattice to 3D whole core, providing the reference solutions for SPERT-III E-Core benchmarks. The complicated geometry of transient rods is modeled by the Constructive Solid Geometry (CSG) method in NECP-X. Numerical results indicate that NECP-X shows the good agreement with KENO-VI for all test cases.

Original language	English
Article number	103322
Journal	Progress in Nuclear Energy
Volume	124
DOIs	https://doi.org/10.1016/j.pnucene.2020.103322
State	Published - Jun 2020

Keywords

KENO-VI
NECP-X
SPERT benchmark

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10.1016/j.pnucene.2020.103322

Cite this

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title = "SPERT III E-Core critical experiment benchmarks calculation with NECP-X and KENO-VI",

abstract = "The Special Power Excursion Reactor Test (SPERT) III E-Core is a small experimental reactor towards experimental and theoretical investigations of kinetic and safety behavior of nuclear reactors. The SPERT III E-core model was established with a high-fidelity direct whole-core transport code NECP-X and a Monte Carlo code KENO-VI. Most of components of the reactor core were explicitly modeled in these two codes. A series of steady-state cases were calculated, ranging from 2D lattice to 3D whole core, providing the reference solutions for SPERT-III E-Core benchmarks. The complicated geometry of transient rods is modeled by the Constructive Solid Geometry (CSG) method in NECP-X. Numerical results indicate that NECP-X shows the good agreement with KENO-VI for all test cases.",

keywords = "KENO-VI, NECP-X, SPERT benchmark",

author = "Chen Zhao and Zhouyu Liu and Lu Cao and Qicang Shen and Thomas Downar and Liangzhi Cao",

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year = "2020",

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doi = "10.1016/j.pnucene.2020.103322",

language = "英语",

volume = "124",

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T1 - SPERT III E-Core critical experiment benchmarks calculation with NECP-X and KENO-VI

AU - Zhao, Chen

AU - Liu, Zhouyu

AU - Cao, Lu

AU - Shen, Qicang

AU - Downar, Thomas

AU - Cao, Liangzhi

PY - 2020/6

Y1 - 2020/6

N2 - The Special Power Excursion Reactor Test (SPERT) III E-Core is a small experimental reactor towards experimental and theoretical investigations of kinetic and safety behavior of nuclear reactors. The SPERT III E-core model was established with a high-fidelity direct whole-core transport code NECP-X and a Monte Carlo code KENO-VI. Most of components of the reactor core were explicitly modeled in these two codes. A series of steady-state cases were calculated, ranging from 2D lattice to 3D whole core, providing the reference solutions for SPERT-III E-Core benchmarks. The complicated geometry of transient rods is modeled by the Constructive Solid Geometry (CSG) method in NECP-X. Numerical results indicate that NECP-X shows the good agreement with KENO-VI for all test cases.

AB - The Special Power Excursion Reactor Test (SPERT) III E-Core is a small experimental reactor towards experimental and theoretical investigations of kinetic and safety behavior of nuclear reactors. The SPERT III E-core model was established with a high-fidelity direct whole-core transport code NECP-X and a Monte Carlo code KENO-VI. Most of components of the reactor core were explicitly modeled in these two codes. A series of steady-state cases were calculated, ranging from 2D lattice to 3D whole core, providing the reference solutions for SPERT-III E-Core benchmarks. The complicated geometry of transient rods is modeled by the Constructive Solid Geometry (CSG) method in NECP-X. Numerical results indicate that NECP-X shows the good agreement with KENO-VI for all test cases.

KW - KENO-VI

KW - NECP-X

KW - SPERT benchmark

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DO - 10.1016/j.pnucene.2020.103322

M3 - 文章

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SN - 0149-1970

VL - 124

JO - Progress in Nuclear Energy

JF - Progress in Nuclear Energy

M1 - 103322

ER -

SPERT III E-Core critical experiment benchmarks calculation with NECP-X and KENO-VI

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Keywords

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