Published March 1996 | Version v1
Report Open

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.

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Additional details

Publishing Information

Imprint Pagination
70 p.
Report number
NUREG/CR--6253

Optional Information

Contract/Grant/Project number
Contract AC02-76CH00016
Funding organization
Nuclear Regulatory Commission, Washington, DC (United States).
Secondary number(s)
BNL-NUREG--52425.