Analysis of the VENUS out-of-core activation measurements using MCBEND

Book · Sat Dec 31 04:00:00 EST 1994

OSTI ID:55600

Blaise, P D; Wouters, R.M. de ^[1]; Abderrahim, H A ^[2]

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1. Tractebel Energy Engineering, Brussels (Belgium)
2. SCK-CEN, Mol (Belgium). Fuel Research Div.

The VENUS-1 critical assembly simulates a UO2-loaded core and the internal structures from the core baffle to the neutron pad, in a generic 3-loop plant. VENUS-2 contained mixed oxide PuO2--UO2 fuel pins in the eight outer rows. Several out-of-core threshold activation rates (In-115, Np-237, Zn-64, Al-27, Ni-58, U-238, Rh-103) have been measured at numerous locations in water zones and steel structures. From these measurements, equivalent fission fluxes have been established by dividing the activation rates by cross-sections weighted by the U-235 fission spectrum. Calculations of equivalent fission fluxes have been carried out with the Monte Carlo transport program (MCBEND). The average ratio calculation/experiment (C/E) in the core barrel, with 80 dosimeters and 7 types of reactions, is 1.02 {+-} 0.03 ({sigma}). Further away from the core, the average C/E in the neutron pad from 13 measurements is 1.01 {+-} 0.08 ({sigma}).

• OSTI ID: 55600
• Report Number(s): CONF-930809--; ISBN 0-8031-1899-6
• Country of Publication: United States
• Language: English

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