Advanced methods comparisons of reaction rates in the Purdue Fast Breeder Blanket Facility
Description
A review of worldwide results revealed that reaction rates in the blanket region are generally underpredicted with the discrepancy increasing with penetration; however, these results vary widely. Experiments in the large uniform Purdue Fast Breeder Blanket Facility (FBBF) blanket yield an accurate quantification of this discrepancy. Using standard production code methods (diffusion theory with 50 group cross sections), a consistent Calculated/Experimental (C/E) drop-off was observed for various reaction rates. A 50% increase in the calculated results at the outer edge of the blanket is necessary for agreement with experiments. The usefulness of refined group constant generation utilizing specialized weighting spectra and transport theory methods in correcting this discrepancy was analyzed. Refined group constants reduce the discrepancy to half that observed using the standard method. The surprising result was that transport methods had no effect on the blanket deviations; thus, transport theory considerations do not constitute or even contribute to an explanation of the blanket discrepancies. The residual blanket C/E drop-off (about half the standard drop-off) using advanced methods must be caused by some approximations which are applied in all current methods. 27 refs., 3 figs., 1 tab
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A03/MF A01 - OSTI; 1 as DE89003887.Files
20037875.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 13 p.
- Report number
- CONF-880911--25
Conference
- Title
- International reactor physics conference.
- Dates
- 18-21 Sep 1988.
- Place
- Jackson Hole, WY (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20037875
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BREEDING BLANKETS; HEAT TRANSFER; HYDRAULICS; NEUTRON FLUX; NEUTRON TRANSPORT THEORY; NUCLEAR REACTION KINETICS; NUMERICAL DATA; O CODES; PLUTONIUM PRODUCTION REACTORS; REACTOR SAFETY; T CODES
- Descriptors DEC
- COMPUTER CODES; DATA; ENERGY TRANSFER; INFORMATION; KINETICS; PRODUCTION REACTORS; RADIATION FLUX; REACTION KINETICS; REACTORS; SAFETY; TRANSPORT THEORY
Optional Information
- Notes
- Portions of this document are illegible in microfiche products.