Development and preliminary verification of the 3D core neutronic code: COCO

Conference · Sun Jul 01 00:00:00 EDT 2012

OSTI ID:22105738

Lu, H.; Mo, K.; Li, W.; Bai, N.; Li, J. ^[1]

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1. Reactor Design and Fuel Management Research Center, China Nuclear Power Technology Research Inst., 47F/A Jiangsu Bldg., Yitian Road, Futian District, Shenzhen (China)

As the recent blooming economic growth and following environmental concerns (China)) is proactively pushing forward nuclear power development and encouraging the tapping of clean energy. Under this situation, CGNPC, as one of the largest energy enterprises in China, is planning to develop its own nuclear related technology in order to support more and more nuclear plants either under construction or being operation. This paper introduces the recent progress in software development for CGNPC. The focus is placed on the physical models and preliminary verification results during the recent development of the 3D Core Neutronic Code: COCO. In the COCO code, the non-linear Green's function method is employed to calculate the neutron flux. In order to use the discontinuity factor, the Neumann (second kind) boundary condition is utilized in the Green's function nodal method. Additionally, the COCO code also includes the necessary physical models, e.g. single-channel thermal-hydraulic module, burnup module, pin power reconstruction module and cross-section interpolation module. The preliminary verification result shows that the COCO code is sufficient for reactor core design and analysis for pressurized water reactor (PWR). (authors)

• Research Organization: American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)
• OSTI ID: 22105738
• Resource Relation: Conference: PHYSOR 2012: Conference on Advances in Reactor Physics - Linking Research, Industry, and Education, Knoxville, TN (United States), 15-20 Apr 2012; Other Information: Country of input: France; 6 refs.
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
BOUNDARY CONDITIONS
BURNUP
CHINA
COMPUTER CODES
COMPUTER GRAPHICS
CROSS SECTIONS
DESIGN
ECONOMIC DEVELOPMENT
GREEN FUNCTION
INTERPOLATION
ITERATIVE METHODS
NEUTRON FLUX
NONLINEAR PROBLEMS
NUCLEAR POWER PLANTS
PWR TYPE REACTORS
REACTOR CORES
THERMAL HYDRAULICS
THREE-DIMENSIONAL CALCULATIONS
VERIFICATION