Abstract
The Venus-1 critical assembly simulates a U02-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 Pu02-U02 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 programme 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 (). Further away from the core, the average C/E in the neutron pad from 13 measurements is 1.01 0.08 ().
Original language | English |
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Title of host publication | ASTM-STP-1228 |
Subtitle of host publication | ASTM-EURATOM symposium on reactor dosimetry |
Pages | 323-332 |
Number of pages | 10 |
Volume | ASTM-STP-1228 |
Edition | 1994 |
State | Published - 31 Dec 1994 |
Event | 1993 - 8th ASTM-EURATOM symposium on reactor dosimetry - Vail Duration: 29 Aug 1993 → 3 Sep 1993 |
Conference
Conference | 1993 - 8th ASTM-EURATOM symposium on reactor dosimetry |
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Country/Territory | United States |
City | Vail |
Period | 1993-08-29 → 1993-09-03 |