Development of NECP-SARAX1.0 code for fast reactor physics calculation

NECP Team

doi:10.13832/j.jnpe.2014.S2.0116

Development of NECP-SARAX1.0 code for fast reactor physics calculation

NECP Team

School of Energy and Power Engineering

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

5 Scopus citations

Abstract

A new code NECP-SARAX1.0 is developed for the nuclear design and steady analysis of the fast reactor core based on the special features of fast reactor physics. The continuous energy cross section library from ENDF/BVII is used. The OPENMC code is adopted to generate the multi-group cross sections. The SN-nodal method transport is applied in the core calculation based on the unstructured mesh modeling. It is suitable for both the critical and subcritical core calculation. The perturbation method is used to calculate the Doppler coefficients. Numerical results show that the new code is of high precision. Compared with direct MCNP calculation, the difference of k_eff is around 100×10^-5.

Original language	English
Pages (from-to)	116-118
Number of pages	3
Journal	Hedongli Gongcheng/Nuclear Power Engineering
Volume	35
DOIs	https://doi.org/10.13832/j.jnpe.2014.S2.0116
State	Published - 15 Dec 2014

Keywords

Continuous energy
Fast reactor
Neutron transport
Physics calculation

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10.13832/j.jnpe.2014.S2.0116

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title = "Development of NECP-SARAX1.0 code for fast reactor physics calculation",

abstract = "A new code NECP-SARAX1.0 is developed for the nuclear design and steady analysis of the fast reactor core based on the special features of fast reactor physics. The continuous energy cross section library from ENDF/BVII is used. The OPENMC code is adopted to generate the multi-group cross sections. The SN-nodal method transport is applied in the core calculation based on the unstructured mesh modeling. It is suitable for both the critical and subcritical core calculation. The perturbation method is used to calculate the Doppler coefficients. Numerical results show that the new code is of high precision. Compared with direct MCNP calculation, the difference of keff is around 100×10-5.",

keywords = "Continuous energy, Fast reactor, Neutron transport, Physics calculation",

author = "\{NECP Team\} and Youqi Zheng and Hongchun Wu",

year = "2014",

month = dec,

day = "15",

doi = "10.13832/j.jnpe.2014.S2.0116",

language = "英语",

volume = "35",

pages = "116--118",

journal = "Hedongli Gongcheng/Nuclear Power Engineering",

issn = "0258-0926",

publisher = "Atomic Energy Press",

}

TY - JOUR

T1 - Development of NECP-SARAX1.0 code for fast reactor physics calculation

AU - NECP Team

AU - Zheng, Youqi

AU - Wu, Hongchun

PY - 2014/12/15

Y1 - 2014/12/15

N2 - A new code NECP-SARAX1.0 is developed for the nuclear design and steady analysis of the fast reactor core based on the special features of fast reactor physics. The continuous energy cross section library from ENDF/BVII is used. The OPENMC code is adopted to generate the multi-group cross sections. The SN-nodal method transport is applied in the core calculation based on the unstructured mesh modeling. It is suitable for both the critical and subcritical core calculation. The perturbation method is used to calculate the Doppler coefficients. Numerical results show that the new code is of high precision. Compared with direct MCNP calculation, the difference of keff is around 100×10-5.

AB - A new code NECP-SARAX1.0 is developed for the nuclear design and steady analysis of the fast reactor core based on the special features of fast reactor physics. The continuous energy cross section library from ENDF/BVII is used. The OPENMC code is adopted to generate the multi-group cross sections. The SN-nodal method transport is applied in the core calculation based on the unstructured mesh modeling. It is suitable for both the critical and subcritical core calculation. The perturbation method is used to calculate the Doppler coefficients. Numerical results show that the new code is of high precision. Compared with direct MCNP calculation, the difference of keff is around 100×10-5.

KW - Continuous energy

KW - Fast reactor

KW - Neutron transport

KW - Physics calculation

UR - https://www.scopus.com/pages/publications/84930520274

U2 - 10.13832/j.jnpe.2014.S2.0116

DO - 10.13832/j.jnpe.2014.S2.0116

M3 - 文章

AN - SCOPUS:84930520274

SN - 0258-0926

VL - 35

SP - 116

EP - 118

JO - Hedongli Gongcheng/Nuclear Power Engineering

JF - Hedongli Gongcheng/Nuclear Power Engineering

ER -

Development of NECP-SARAX1.0 code for fast reactor physics calculation

Abstract

Keywords

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