Published April 2017 | Version v1
Book

Development of whole Core thermal hydraulic analysis code CORTH

  • 1. Nuclear Power Institute of China, Chengdu, 610213 (China)
  • 2. Science and technology on reactor system design technology, Nuclear Power Institute of China, Chengdu, 610041 (China)

Description

Subchannel program is the main tool for the core thermal hydraulic analysis. By dividing the core into a series of connected or disconnected channels, the sub channel program can calculate the enthalpy field and the flow field of the core, and further calculate the core DNBR. The whole Core Thermal Hydraulic analysis program CORTH V1.5 is based on CORTH V1.0.Through the code core matrix algorithm optimization and parallel method, CORTH V1.5 is used to analyze the subchannel of the large scale mode, describing the distribution of thermal parameters of 3D core and give detailed feedback parameters for fuel and Neutron kinetics code.The paper shows that CORTH v1.5 With a high computational efficiency, and give the correct calculation results. (authors)

Additional details

Publishing Information

Publisher
Korean Nuclear Society - KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Pagination
5 p.

Conference

Title
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering 2017
Acronym
M and C 2017
Dates
16-20 Apr 2017
Place
Jeju (Korea, Republic of)

Optional Information

Notes
4 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses