Neutron and gamma-ray flux calculations for the VENUS PWR engineering mockup

Conference · Wed Jan 01 04:00:00 EST 1986 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:6995132

Fero, A H

This paper describes the analysis of neutron and gamma-ray fluxes in the VENUS pressurized water reactor (PWR) engineering mockup benchmark experiment (SCK/CEN Mol, Belgium). This mockup is unique in two ways. It is the first mockup to correctly represent the heterogeneities which exist in the PWR core peripheral fuel assemblies, core baffle, core barrel, and neutron pad. This is accomplished by using low-enrichment (3.3 and 4.0 wt% /sup 235/U) fuel pins and a representative PWR fuel assembly geometry (15 x 15) with full thickness Type 304 stainless steel reactor internals structures located with representative water gap spacing. The VENUS mockup also represents locally the stairstep geometry of the core periphery. Second, the VENUS mockup is extremely well characterized in terms of as-built dimensions, material compositions, and pin-by-pin core power distributions. Analysis of VENUS was performed using the methods and procedures used to analyze commercial PWRs. Specifically, two-dimensional discrete-ordinates transport theory calculations were performed using the DOT-IIIW code.

• Research Organization: Westinghouse NTSD
• OSTI ID: 6995132
• Report Number(s): CONF-861102-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 53
• Country of Publication: United States
• Language: English

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