In-core and ex-core calculations of the VENUS simulated PWR benchmark experiment

Conference · Fri Nov 01 04:00:00 EST 1985 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:5860008

Williams, M L; Chowdhury, P; Landesman, M; Kam, F B.K.

The VENUS pressurized water reactor (PWR) engineering mockup experiment was established to simulate a beginning-of-life, generic PWR configuration at the zero-power VENUS critical facility located at CEN/SCK in Mol, Belgium. The reactor contains Zircaloy-clad, low-enriched UO/sub 2/ pins in a light water moderator. The size and pitch of the pins are consistent with modern PWR cores. The VENUS rectangular core region is surrounded by a steel baffle, followed by a water reflector, a simulated core barrel, a simulated thermal shield, and a simulated downcomer region, respectively. The US Nuclear Regulatory Commission has supported dosimetry measurements and calculations in this Belgium-sponsored benchmark experiment as part of its light water (LWR) reactor pressure vessel (RPV) surveillance dosimetry improvement program to determine the accuracy to which neutron and gamma responses can be calculated in a prototypic LWR environment.

• Research Organization: Louisiana State Univ., Baton Rouge
• OSTI ID: 5860008
• Report Number(s): CONF-851115-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 50
• Country of Publication: United States
• Language: English

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