Validation of accelerator driven subcritical reactors utilizing MCNP code

Wen Chao Hu; Xiao Ping Ouyang; Bin Liu; Kai Wang; Li Ming Huang

Validation of accelerator driven subcritical reactors utilizing MCNP code

Wen Chao Hu
, Xiao Ping Ouyang
, Bin Liu
, Kai Wang
, Li Ming Huang

North China Electric Power University
Northwest Institute of Nuclear Technology

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

Abstract

In this paper, some characteristics of the ADS subcritical reactor core is described using the Monte Carlo code (MCNP). The K_eff value, neutron energy spectrum and neutron flux of a ADS system are obtained by the MCNP code under certain ADS core size as the ADS target and coolant are lead, lead-bismuth alloy, bismuth and mercury respectively. The data and the ADS system parameters obtained from the MCNP simulation calculation are compared and analyzed. The results show that the lead-bismuth alloy is the best material for ADS target and coolant among all the materials tested.

Original language	English
Pages (from-to)	12-15
Number of pages	4
Journal	Hedongli Gongcheng/Nuclear Power Engineering
Volume	34
Issue number	4
State	Published - Aug 2013
Externally published	Yes

Keywords

ADS
K
Lead
Lead-bismuth alloy
MCNP Code

Cite this

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title = "Validation of accelerator driven subcritical reactors utilizing MCNP code",

abstract = "In this paper, some characteristics of the ADS subcritical reactor core is described using the Monte Carlo code (MCNP). The Keff value, neutron energy spectrum and neutron flux of a ADS system are obtained by the MCNP code under certain ADS core size as the ADS target and coolant are lead, lead-bismuth alloy, bismuth and mercury respectively. The data and the ADS system parameters obtained from the MCNP simulation calculation are compared and analyzed. The results show that the lead-bismuth alloy is the best material for ADS target and coolant among all the materials tested.",

keywords = "ADS, K, Lead, Lead-bismuth alloy, MCNP Code",

author = "Hu, \{Wen Chao\} and Ouyang, \{Xiao Ping\} and Bin Liu and Kai Wang and Huang, \{Li Ming\}",

year = "2013",

month = aug,

language = "英语",

volume = "34",

pages = "12--15",

journal = "Hedongli Gongcheng/Nuclear Power Engineering",

issn = "0258-0926",

publisher = "Atomic Energy Press",

number = "4",

}

TY - JOUR

T1 - Validation of accelerator driven subcritical reactors utilizing MCNP code

AU - Hu, Wen Chao

AU - Ouyang, Xiao Ping

AU - Liu, Bin

AU - Wang, Kai

AU - Huang, Li Ming

PY - 2013/8

Y1 - 2013/8

N2 - In this paper, some characteristics of the ADS subcritical reactor core is described using the Monte Carlo code (MCNP). The Keff value, neutron energy spectrum and neutron flux of a ADS system are obtained by the MCNP code under certain ADS core size as the ADS target and coolant are lead, lead-bismuth alloy, bismuth and mercury respectively. The data and the ADS system parameters obtained from the MCNP simulation calculation are compared and analyzed. The results show that the lead-bismuth alloy is the best material for ADS target and coolant among all the materials tested.

AB - In this paper, some characteristics of the ADS subcritical reactor core is described using the Monte Carlo code (MCNP). The Keff value, neutron energy spectrum and neutron flux of a ADS system are obtained by the MCNP code under certain ADS core size as the ADS target and coolant are lead, lead-bismuth alloy, bismuth and mercury respectively. The data and the ADS system parameters obtained from the MCNP simulation calculation are compared and analyzed. The results show that the lead-bismuth alloy is the best material for ADS target and coolant among all the materials tested.

KW - ADS

KW - K

KW - Lead

KW - Lead-bismuth alloy

KW - MCNP Code

UR - https://www.scopus.com/pages/publications/84884483517

M3 - 文章

AN - SCOPUS:84884483517

SN - 0258-0926

VL - 34

SP - 12

EP - 15

JO - Hedongli Gongcheng/Nuclear Power Engineering

JF - Hedongli Gongcheng/Nuclear Power Engineering

IS - 4

ER -

Validation of accelerator driven subcritical reactors utilizing MCNP code

Abstract

Keywords

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