Coupling analysis on a new SCWR core design

International Conference on Advances in Nuclear Power Plants, ICAPP 2008

Volumn 2, Issue , 2008, Pages 700-707

  Liu, X J ^a   Cheng, X ^a  

^a SHANGHAI JIAO TONG UNIVERSITY   (China)

Author keywords

Core design; Coupling analysis; SCWR

Indexed keywords

CORE CALCULATIONS; CORE DESIGN; COUPLING ANALYSIS; COUPLING PROCEDURE; DIFFUSION CODE; FISSILE FUELS; FUEL ASSEMBLY; HEAT TRANSFER CORRELATION; LINEAR POWER DENSITIES; MASS FLOW; NEUTRONICS; PHYSICAL PERFORMANCE; RADIAL POWER PROFILE; SCWR; SENSITIVITY STUDIES; SUBCHANNEL ANALYSIS; THERMAL HYDRAULICS; THERMAL POWER;

FUELS; NEUTRONS; NUCLEAR ENERGY; NUCLEAR INDUSTRY; NUCLEAR POWER PLANTS; THREE DIMENSIONAL;

WATER COOLED REACTORS;

EID: 70349976489     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (5)

1. Y Oka, Review of high temperature water and steam cooled reactor concepts, Proc. of SCR-2000, Tokyo, (2000).
2. X.J. Liu, X. Cheng, Neutron-Physical and Thermal-Hydraulic Characteristics of a New SCWR Fuel Assembly, Proceedings of ICAPP '07, Nice, France, paper 7423, (2007 ).
3. X. Cheng, T. Schulenberg, Heat Transfer at Supercritical Pressures-Literature Review and Application to an HPLWR, FZK report NO. 6609, (2001).
4. K. Kamel, A. Yamaji, Y. Ishiwatarl, Fuel and Core Design of Super LWR with Stainless Steel Cladding, Proceedings of ICAPP '05 Seoul, KOREA, paper 5527, (2005).
5. A. Yamaji, K. Kamei, Y. Oka, S. Koshizuka, Improved Core Design of the High Temperature Supercritical-Pressure Light Water Reactor, Annals of Nuclear Energy, Vol.32, 7, 651, (2005)