A STUDY OF WET STEAM AS A REACTOR COOLANT. Quarterly Technical Progress Report No. 1, October 1, 1959 through December 31, 1959
Technical Report
·
OSTI ID:4818812
Reactor conceptual designs of fog-cooled, watermoderated reactors are presented. The effects of variables such as burnout, pressure, mass velocity, and steam quality are discussed; they serve as a basis for guiding a series of heat transfer and fluid dynamics tests. The results of a brief study of the phenomenon of burnout as it applies to wet steam as a reactor coolant are presented. A reactivity formulation for use in this project is also presented. (auth)
- Research Organization:
- Nuclear Development Corp. of America. White Plains, N.Y.
- NSA Number:
- NSA-16-018618
- OSTI ID:
- 4818812
- Report Number(s):
- NDA-2132-2; EURAEC-100
- Country of Publication:
- United States
- Language:
- English
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