Development of SNTA Code System for SCWR Core Steady-State Analysis-Reference-Cited by-同舟云学术

Development of SNTA Code System for SCWR Core Steady-State Analysis

Published:2017-03-01 Issue:2 Volume:3 Page:
ISSN:2332-8983
Container-title:Journal of Nuclear Engineering and Radiation Science
language:en
Short-container-title:

Author:

Wang Lianjie¹,Zhao Wenbo¹,Yang Ping¹,Ma Yongqiang¹,Lu Di¹

Affiliation:

1. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, No. 328, Section 1, Changshun Avenue, Shuangliu County, Chengdu 610213, China e-mail:

Abstract

A coupled neutronics/thermal-hydraulics (N/T) three-dimensional code system SNTA is developed for supercritical water-cooled reactor (SCWR) core steady-state analysis by modular coupling the improved neutronics nodal methodological code and SCWR thermal-hydraulic subchannel code. The appropriate outer iteration coupling method and self-adaptive relaxation factor are proposed for enhancing convergence, stability, and efficiency of coupled N/T calculation. The steady-state analysis for the CSR1000 core is applied to verify SNTA. The results calculated by SNTA agreed well with those by CASIR and SRAC. SNTA is more efficient than CASIR and SRAC, where the neutronics modules are based on the finite-difference method. The numeric results show that SNTA can be applied to SCWR core steady-state analysis and core concept design.

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Link

http://asmedigitalcollection.asme.org/nuclearengineering/article-pdf/doi/10.1115/1.4035334/6067410/ners_003_02_021005.pdf

Reference13 articles.

1. Three-Dimensional Core Design of High Temperature Supercritical-Pressure Light Water Reactor With Neutronics and Thermal-Hydraulic Coupling;J. Nucl. Sci. Technol.,2006

2. Supercritical Water Nuclear Steam Supply System: Innovation in Materials, Neutronics and Thermal-Hydraulics,2004

3. HPLWR Equilibrium Core Design With the KARATE Code System;Prog. Nucl. Energy,2011

4. Assessment of the Traditional Neutron-Diffusion Core-Analysis Method for the Analysis of the Super Critical Water Reactor;Ann. Nucl. Energy,2012

5. Development of Coupled Neutronics/Thermal-Hydraulics CASIR Code System for SCWR Core Steady State;Nucl. Power Eng.,2013

Cited by 3 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Three-dimensional transient analysis for control rods drop into CSR1000 core;Annals of Nuclear Energy;2021-04

2. Study on Calculation Difference of the SCWR Core Steady-State Analysis Code;Journal of Nuclear Engineering and Radiation Science;2020-06-05

3. Study on Optimization Design for CSR1000 Core;Journal of Nuclear Engineering and Radiation Science;2017-12-04