Published July 1984
| Version v1
Report
Neutronics calculations in support of the OOR-MFE-4A and -4B spectral tailoring experiments
Description
The objective of this work was to provide the neutronic design for materials irradiation experiments in the Oak Ridge Research Reactor (ORR). Spectral tailoring to control the fast and thermal fluxes is required to provide the desired displacement and helium production rates in alloys containing nickel. The calculated fluences from the ongoing three-dimensional neutronics calculations are being scaled to agree with experimental data. As of March 27, 1984, this treatment yields 158.5 at. ppm He (not including 2.0 at. ppm He from 10B) and 10.36 dpa for type 316 stainless steel in ORR-MFE-4A and 99.4 at. ppm He and 7.10 dpa in ORR-MFE-4B
Additional details
Publishing Information
- Imprint Title
- Alloy development for irradiation performance. Semiannual progress report for period ending March 31, 1984
- Journal Page Range
- p. 22-23.
- Report number
- DOE/ER--0045/12
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16065840
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE;
- Descriptors DEI
- FIRST WALL; HELIUM; PHYSICAL RADIATION EFFECTS; PRODUCTION; STEEL-CR17NI12MO3
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STE; CORROSION RESISTANT ALLOYS; ELEMENTS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NONMETALS; RADIATION EFFECTS; RARE GASES; STAINLESS STEELS; STEELS; THERMONUCLEAR REACTOR WALLS