NUCLEAR SUPERHEAT PROJECT THIRTEENTH QUARTERLY REPORT, JULY-SEPTEMBER 1962
The design study of a 600 Mw(e) boiling water-separate superheat reactor plant was completed. In addition a refueling accident was investigated and summarized. A parametric evaluation of fuel bundle bowing produced by nonuniform cladding temperature is summarized. Irradiation of the first fuel loading, ESH- 1, for the E-SADE loop began. The BONUS fuel element was tested in preparation to being placed in the ESH-2 assembly. Metallographic examination of the NUSU cladding, Inconel X and type 347 stainless steel, revealed no localized corrosion attack on either material. No leak in the NUSU cladding was found. The effect of a superheat environment on the mechanical properties of Hastelloy X, Incoloy, and Inconel is shown. The additional effect of radiation is also shown. Corrosion testing in boiling MgCl/sub 2/ showed Hastelloy X and Inconel 625 to be the most resistant to the corrosion attack. Strain cycle results for nickel alloys at 1300 deg F are shown. Cycle and corrosion tests with heat transfer were run on Incoloy, Hastelloy X, and type 408 stainless steel. Further redesign of the CL-1 facility has begin with the goal of raising the steam temperature to 1150 deg F and clad temperature to 1400 deg F. Results are given for a series of air-water tests of the full-circle radial-vane separator showing the detailed flow on the vessel wall simulator at different air and water flow rates, different water level, and with 8 or 12 nozzles. The design conditions for ESH-2 are given. Work was initiated on a more detailed description of the long range Mixed Spectrum Superheat Reactor aiming toward a 500 Mw(e) plant. The conceptual design of the MSCA was completed. The development program for MSCA is described. (N.W.R.)
- Research Organization:
- General Electric Co. Atomic Power Equipment Dept., San Jose, Calif.
- NSA Number:
- NSA-17-036928
- OSTI ID:
- 4660176
- Report Number(s):
- GEAP-4126
- Country of Publication:
- United States
- Language:
- English
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GENERAL AND STRESS CORROSION OF HIGH NICKEL ALLOYS IN SIMULATED SUPERHEAT REACTOR ENVIRONMENT
NUCLEAR SUPERHEAT PROJECT FIFTEENTH QUARTERLY REPORT, JANUARY-MARCH 1963
Related Subjects
ALUMINUM ALLOYS
BOILING
BONUS
CHROMIUM ALLOYS
COOLANT LOOPS
CORROSION
DEFORMATION
FINS
FLUID FLOW
FUEL CANS
FUEL ELEMENTS
HASTELLOY
HEAT TRANSFER
HIGH TEMPERATURE
INCOLOY
INCONEL ALLOYS
IRON ALLOYS
IRRADIATION
LEAKS
MAGNESIUM CHLORIDES
MATERIALS TESTING
METALLOGRAPHY
MOLYBDENUM ALLOYS
MSCA
NICKEL ALLOYS
NIOBIUM ALLOYS
NOZZLES
NUSU
PLANNING
POWER PLANTS
REACTOR TECHNOLOGY
STAINLESS STEELS
SUPERHEATING
TEMPERATURE
TESTING
TITANIUM ALLOYS
WATER COOLANT
WATER MODERATOR