Development and validation of reactor nuclear design code CORCA-3D

Ping An; Yongqiang Ma; Peng Xiao; Fengchen Guo; Wei Lu; Xiaoming Chai

Nuclear Engineering and Technology (Oct 2019)

Development and validation of reactor nuclear design code CORCA-3D

Ping An,
Yongqiang Ma,
Peng Xiao,
Fengchen Guo,
Wei Lu,
Xiaoming Chai

Affiliations

Ping An: Corresponding author.; Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China
Yongqiang Ma: Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China
Peng Xiao: Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China
Fengchen Guo: Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China
Wei Lu: Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China
Xiaoming Chai: Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Journal volume & issue: Vol. 51, no. 7
pp. 1721 – 1728

Abstract

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The advanced node core code CORCA-3D is one of the independent developed codes of NPIC for the nuclear reactor core design. CORCA-3D code can calculate the few-group cross section, solve the 3D diffusion equations, consider the thermal-hydraulic feedback, reconstruct the pin-by-pin power. It has lots of functions such as changing core status calculation, critical searching, control rod value calculation, coefficient calculation and so on. The main theory and functions of CORCA-3D code are introduced and validated with a lot of reactor measured data and the SCIENCE system. Now, CORCA-3D code has been applied in ACP type reactor nuclear cores design. Keywords: Nuclear design, Diffusion calculation, Critical boron concentration, Thermal-hydraulic feedback, Science

Published in Nuclear Engineering and Technology

ISSN: 1738-5733 (Print)
Publisher: Elsevier
Country of publisher: Korea, Republic of
LCC subjects: Technology: Electrical engineering. Electronics. Nuclear engineering: Nuclear engineering. Atomic power
Website: http://www.journals.elsevier.com/nuclear-engineering-and-technology

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