630A MARITIME NUCLEAR STEAM GENERATOR. Progress Report No. 1
Work on the 630A Maritime Nuclear Steam Generator Scoping Study is summarized. The objective of the program is to establish a specific 630A configuration and to develop specifications for components and test equipment. During the period, work was initiated in critical experiment design and fabrication, additional fuel and materials investigations, boiler-test design and fabrication; blower studies; design of component tests; nuclear, thermodynamic, mechanical and safety analysis, and test facility and equipment studies. Design of the critical experiment mockup and test equipment was completed and fabrication of the parts is approximately 50% complete. A rough draft of the critical experiment hazards report was completed. A fuel test in the ORR completed 876.5 hr of testing out of a planned 2200-hr test without indication of failure. The burnup was equivalent to about 6000 hr of 630A operation. Damage to the capsule during refueling of the ORR caused termination of the test. The design of an MTR fuel-burnup test was completed and fabrication of the sample initiated. Ni-Cr fuel sheet and cladding stock are being tested for creep and oxidation properties at temperatures up to 1750 deg F and have accumulated times up to 5000 hr; no failures have occurred. These tests are continuing. Specimens of Ni-Cr were fabricated and will be tested to determine the effect of neutron irradiation. Cycle operating conditions with 120O deg F reactor-discharge-air temperature were studied and found to be acceptable for the proposed maritime application. Increases in cycle efficiency above 30.2% appear to be possible and practical. Studies during the period indicate that an acceptable power distribution can be maintained through the life of the reactor and the maximum hot spot temperature and maximum burnup location would not coincide. Specifications for the fuel loading of the critical experiment are being prepared. Study of the pressure vessel resulted in selection of 304 SS. Containment studies indfcated the practicality of designing the shield tank outer shell as part of the containment vessel. A blower scoping study subcontract was completed. The study verified the feasibility of the main and afterblower concept. Alternate shaft-seal designs were proposed. The design of a performance test for the two seal types has been initiated. The design of the boiler test from which control characteristics will be determined was completed and fabrication started. The decision was made that the Low Power Test Facility (LPTF) will be the site used for the critical experiment. A preliminary study of the power test facility requirements were completed. The study indicated that locating the facility adjacent to the LPTF would be operationally and economically feasible. (auth)
- Research Organization:
- General Electric Co. Flight Propulsion Laboratory Dept., Cincinnati, OH
- Sponsoring Organization:
- US Atomic Energy Commission (AEC)
- DOE Contract Number:
- AT(40-1)-2847
- NSA Number:
- NSA-16-030068
- OSTI ID:
- 4772139
- Report Number(s):
- GEMP-130
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-62
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
AIR
BURNUP
CHROMIUM ALLOYS
COMPRESSORS
CONFIGURATION
CONFINEMENT
CONTAINMENT
CONTROL
CREEP
CRITICAL ASSEMBLIES
CRITICALITY
DISTRIBUTION
ECONOMICS
EFFICIENCY
FABRICATION
FUEL ELEMENTS
GAS FLOW
GENERATORS
HIGH TEMPERATURE
IRRADIATION
LABORATORY EQUIPMENT
MACHINE PARTS
MATERIALS TESTING
MOCKUP
NEUTRON FLUX
NEUTRONS
NICKEL ALLOYS
OXIDATION
PLANNING
POWER
PRESSURE VESSELS
PROPULSION
REACTOR SAFETY
REACTORS
SEALS
SHIELDING
SHIPS
STAINLESS STEELS
STEAM
TESTING
THERMODYNAMICS