Systems Design of Direct-Cycle Supercritical-Water-Cooled Fast Reactors
Author:
Affiliation:
1. The University of Tokyo Nuclear Engineering Research Laboratory Tokai-Mura, Naka-Gun, Ibaraki 319-11, Japan
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT95-A35064
Reference6 articles.
1. Concept and Design of a Supercritical-Pressure, Direct-Cycle Light Water Reactor
2. Effect of Zirconium-Hydride Layers on Reducing Coolant Void Reactivity of Steam Cooled Fast Breeder Reactors
3. Large-break loss-of-collant accident analysis of a direct-cycle supercritical-pressure light water reactor
4. F. D. COFFMAN, Jr. “LOCA Temperature Criterion for Stainless Steel Clad Fuel,” NUREG-0065, U.S. Nuclear Regulatory Commission (1976).
5. I. M. KEYFITZ et al. “1000 MWe Supercritical-Pressure Nuclear Power Plant Design Study,” WCAP-2240, Westinghouse Electric Corporation (1964).
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