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

Hamid Aït Abderrahim; Patrick D. Blaise; Wim De Boeck

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

Hamid Aït Abderrahim, Patrick D. Blaise, Wim De Boeck

Research output › peer-review

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
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
Country/Territory	United States
City	Vail
Period	1993-08-29 → 1993-09-03

Cite this

@inproceedings{7ac0a629328744e89fd9423e728c0782,

title = "Analysis of the VENUS out-of-core activation measurements using MCBEND",

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 ().",

keywords = "critical facility, threshold activities, Monte-Carlo",

author = "{A{\"i}t Abderrahim}, Hamid and Blaise, {Patrick D.} and {De Boeck}, Wim",

year = "1994",

month = dec,

day = "31",

language = "English",

isbn = "0-8031-1899-6",

volume = "ASTM-STP-1228",

pages = "323--332",

booktitle = "ASTM-STP-1228",

edition = "1994",

note = "1993 - 8th ASTM-EURATOM symposium on reactor dosimetry ; Conference date: 29-08-1993 Through 03-09-1993",

}

TY - GEN

T1 - Analysis of the VENUS out-of-core activation measurements using MCBEND

AU - Aït Abderrahim, Hamid

AU - Blaise, Patrick D.

AU - De Boeck, Wim

PY - 1994/12/31

Y1 - 1994/12/31

N2 - 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 ().

AB - 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 ().

KW - critical facility

KW - threshold activities

KW - Monte-Carlo

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/axs_16783

M3 - In-proceedings paper

SN - 0-8031-1899-6

VL - ASTM-STP-1228

SP - 323

EP - 332

BT - ASTM-STP-1228

T2 - 1993 - 8th ASTM-EURATOM symposium on reactor dosimetry

Y2 - 29 August 1993 through 3 September 1993

ER -