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

Conference · Fri Nov 01 00:00:00 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-; TRN: 86-017853
• Journal Information: Trans. Am. Nucl. Soc.; (United States), Vol. 50; Conference: American Nuclear Society winter meeting, San Francisco, CA, USA, 10 Nov 1985
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PRESSURE VESSELS
SURVEILLANCE
PWR TYPE REACTORS
REACTOR KINETICS
BENCHMARKS
VENUS REACTOR
FUEL PINS
NEUTRON DOSIMETRY
NEUTRON SPECTROMETERS
NEUTRON TRANSPORT THEORY
POWER DENSITY
REACTOR CORES
REACTOR LATTICES
SHIELDING
THERMOLUMINESCENT DOSEMETERS
URANIUM DIOXIDE
US NRC
ZIRCALOY
ACTINIDE COMPOUNDS
ALLOYS
CHALCOGENIDES
CONTAINERS
DOSEMETERS
DOSIMETRY
ENRICHED URANIUM REACTORS
EXPERIMENTAL REACTORS
FUEL ELEMENTS
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
KINETICS
LUMINESCENT DOSEMETERS
MEASURING INSTRUMENTS
NATIONAL ORGANIZATIONS
OXIDES
OXYGEN COMPOUNDS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SPECTROMETERS
TANK TYPE REACTORS
THERMAL REACTORS
TIN ALLOYS
TRANSPORT THEORY
URANIUM COMPOUNDS
URANIUM OXIDES
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled