MIF-SKD computation code for thermohydraulic design of a reactor core cooled by supercritical-pressure water-Reference-Cited by-同舟云学术

MIF-SKD computation code for thermohydraulic design of a reactor core cooled by supercritical-pressure water

Published:2009-03 Issue:3 Volume:56 Page:214-217
ISSN:0040-6015
Container-title:Thermal Engineering
language:en
Short-container-title:Therm. Eng.

Author:

Bogoslovskaya G. P.,Karpenko A. A.,Kirillov P. L.,Sorokin A. P.

Publisher

Pleiades Publishing Ltd

Subject

Energy Engineering and Power Technology,Nuclear Energy and Engineering

Link

http://link.springer.com/content/pdf/10.1134/S0040601509030057.pdf

Reference15 articles.

1. Y. Oka and S. Koshizuka, “Design Concept of Once-Through Cycle Supercritical Pressure Light Water Cooled Reactors,” in Proc. of the First Int. Symposium on Supercritical Water-Cooled Reactors, Design and Technology. Tokyo, Japan. 2000. Rep. 101. P. 1–22.

2. G. Heusener, M. Muller, T. Schulenberg, and D. Squarer, “A European Development Program for a High Performance Light Water Reactor (HPLWR),” in Proc. of the First Int. Symposium on Supercritical Water-Cooled Reactors, Design and Technology. Tokyo, Japan. 2000. Rep. 102. P. 23–28.

3. S. J. Bushby, G. R. Dimmick, R. B. Duffey, et al., “Conceptual Design for Advanced, High-Temperature CANDU Reactors,” in Proc. of the First Int. Symposium on Supercritical Water-Cooled Reactors, Design and Technology. Tokyo, Japan. 2000. Rep. 103. P. 29–36.

4. Y. Oka, “Review High Temperature Water and Steam Cooled Reactor Concept,” in Proc. of the First Int. Symposium on Supercritical Water-Cooled Reactors, Design and Technology. Tokyo, Japan. 2000. Rep. 104. P. 37–57.

5. V. A. Grabezhnaya and P. L. Kirillov, “On Calculations of Heat Transfer in Tubes and Rod Bundles under Supercritical-Pressure Water Flow,” Review FEI-0297, (TsNIIatominform, Moscow, 2003).