PIUS core performance analysis
Description
A detailed evaluation of the fuel-burnup dependent power distribution and the scram reactivity for the PIUS reactor design has been performed. The analyses were carried out using the CPM lattice physics and NODE-P2 core neutronics/thermal-hydraulics codes, and are based on the information provided in the PIUS Preliminary Safety Information Document. Cycle depletion calculations were performed for a set of nine representative initial core loadings and the three-dimensional core power distributions were determined. These calculations indicate that the PIUS radial FΔh and total FQ power peaking is stronger than that indicated by the PIUS reference-design values. The scram reactivity resulting from the injection of highly borated pool water was calculated for a series of time-dependent linear ramp and square-wave pool flows. The three-dimensional distribution of the borated pool water throughout the core was modeled and the spatial reactivity effects of the distributed boron were determined. For pool flows that increase as a linear ramp, the spatial reactivity effects of the distributed boron were very small. In this case, a constant core-average boron reactivity coefficient can be used to model the PIUS scram reactivity
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as TI96011104; NTIS; GPO.Files
27063066.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 70 p.
- Report number
- NUREG/CR--6253
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27063066
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- BURNUP; DIAGRAMS; FUEL PINS; N CODES; NUMERICAL DATA; POWER DISTRIBUTION; PWR TYPE REACTORS; REACTIVITY COEFFICIENTS; SOLUBLE POISONS; TEMPERATURE COEFFICIENT
- Descriptors DEC
- COMPUTER CODES; DATA; DISTRIBUTION; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; INFORMATION; MATERIALS; NUCLEAR POISONS; POWER REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SPATIAL DISTRIBUTION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC02-76CH00016
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- BNL-NUREG--52425.