MSRE DESIGN AND OPERATIONS REPORT. PART V-A. SAFETY ANALYSIS OF OPERATION WITH $sup 233$U.
- Research Organization:
- Oak Ridge National Lab., Tenn.
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-22-014140
- OSTI ID:
- 4559773
- Report Number(s):
- ORNL-TM--2111
- Country of Publication:
- United States
- Language:
- English
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CHROMIUM ALLOYS
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CONTROL ELEMENTS
DESIGN
FUELS
HASTELLOY
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IRRADIATION
LEAKS
LOADING
MECHANICAL PROPERTIES
MOLTEN SALT REACTOR EXPERIMENT/containment system for
safety of
MOLTEN SALT REACTOR EXPERIMENT/fuel salts for
description of
MOLTEN SALT REACTOR EXPERIMENT/fuels for
neutronic characteristics with uranium-233 and uranium-235
MOLTEN SALT REACTOR EXPERIMENT/operations history of
total
MOLTEN SALT REACTOR EXPERIMENT/piping and containers in
use of Hastelloy-N for
MOLTEN SALT REACTOR EXPERIMENT/response to load changes
MOLTEN SALT REACTOR EXPERIMENT/safety analyses for uranium-233 fueled
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analysis of
MOLYBDENUM ALLOYS
MSRE
N38180* --Power Reactor Development--Safety & Siting
NEUTRONS
NICKEL ALLOYS
NUMERICALS
OPERATION
PIPES
PRODUCTION
REACTIVITY
REACTOR SAFETY
REACTORS
RESPONSE
RODS
SAFETY
SALTS
SENSITIVITY
URANIUM 233
URANIUM 235
URANIUM ISOTOPES U-233/ production for MSRE
USES