Assessing the Effects of Radiation Damage on Ni-base Alloys for the Prometheus Space Reactor System
Ni-base alloys were considered for the Prometheus space reactor pressure vessel with operational parameters of {approx}900 K for 15 years and fluences up to 160 x 10{sup 20} n/cm{sup 2} (E > 0.1 MeV). This paper reviews the effects of irradiation on the behavior of Ni-base alloys and shows that radiation-induced swelling and creep are minor considerations compared to significant embrittlement with neutron exposure. While the mechanism responsible for radiation-induced embrittlement is not fully understood, it is likely a combination of helium embrittlement and solute segregation that can be highly dependent on the alloy composition and exposure conditions. Transmutation calculations show that detrimental helium levels would be expected at the end of life for the inner safety rod vessel (thimble) and possibly the outer pressure vessel, primarily from high energy (E > 1 MeV) n,{alpha} reactions with {sup 58}Ni. Helium from {sup 10}B is significant only for the outer vessel due to the proximity of the outer vessel to the BeO control elements. Recommendations for further assessments of the material behavior and methods to minimize the effects of radiation damage through alloy design are provided.
- Research Organization:
- Knolls Atomic Power Lab. (KAPL), Niskayuna, NY (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- DE-AC12-00SN39357
- OSTI ID:
- 881302
- Report Number(s):
- LM-06K033; TRN: US0602906
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
42 ENGINEERING
72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS
ALLOYS
CONTROL ELEMENTS
EMBRITTLEMENT
HELIUM
HELIUM EMBRITTLEMENT
IRRADIATION
NEUTRONS
PRESSURE VESSELS
RADIATIONS
SCRAM RODS
SEGREGATION
SOLUTES
SWELLING
TRANSMUTATION
NESDPS Office of Nuclear Energy Space and Defense Power Systems