Analysis of the venus out-of-core activation measurements using mcbend

Patrick D. Blaise; Roger M. De Wouters; Hamid Ait Abderrahim

doi:10.1520/STP15125S

Analysis of the venus out-of-core activation measurements using mcbend

Patrick D. Blaise, Roger M. De Wouters, Hamid Ait Abderrahim

Research output › peer-review

Abstract

The VENUS-I critical assembly simulates a U02-1oaded core and the internal structures from the core baffle to the neutron pad, in a generic 3-1oop plant. VENUS-2 contained mixed oxide PuO2 - UO2 fuel pins in the eight outer rows. Several out-of-core threshold activation rates (In-ll5, Np-237, Zn-64, AI-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 (σ). Further away from the core, the average C/E in the neutron pad from 13 measurements is 1.01 ± 0.08 (σ).

Original language	English
Title of host publication	Reactor Dosimetry
Editors	Harry Farrar, E. Parvin Lippincott, John G. Williams, David W. Vehar
Publisher	American Society for Testing and Materials
Pages	323-332
Number of pages	10
ISBN (Electronic)	9780803118997
DOIs	https://doi.org/10.1520/STP15125S
State	Published - 1994
Event	1993 - 8th ASTM-EURATOM symposium on reactor dosimetry - Vail Duration: 29 Aug 1993 → 3 Sep 1993

Publication series

Name	ASTM Special Technical Publication
Volume	STP 1228
ISSN (Print)	0066-0558

Conference

Conference	1993 - 8th ASTM-EURATOM symposium on reactor dosimetry
Country/Territory	United States
City	Vail
Period	1993-08-29 → 1993-09-03

ASJC Scopus subject areas

General Materials Science

Access to Document

10.1520/STP15125S

Cite this

@inproceedings{759b57a0d2c44dd4a0d7b9bf6d49bc51,

title = "Analysis of the venus out-of-core activation measurements using mcbend",

abstract = "The VENUS-I critical assembly simulates a U02-1oaded core and the internal structures from the core baffle to the neutron pad, in a generic 3-1oop plant. VENUS-2 contained mixed oxide PuO2 - UO2 fuel pins in the eight outer rows. Several out-of-core threshold activation rates (In-ll5, Np-237, Zn-64, AI-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 (σ). Further away from the core, the average C/E in the neutron pad from 13 measurements is 1.01 ± 0.08 (σ).",

keywords = "critical facility, Monte Carlo, threshold activation",

author = "Blaise, \{Patrick D.\} and \{De Wouters\}, \{Roger M.\} and Abderrahim, \{Hamid Ait\}",

year = "1994",

doi = "10.1520/STP15125S",

language = "English",

series = "ASTM Special Technical Publication",

publisher = "American Society for Testing and Materials",

pages = "323--332",

editor = "Harry Farrar and Lippincott, \{E. Parvin\} and Williams, \{John G.\} and Vehar, \{David W.\}",

booktitle = "Reactor Dosimetry",

address = "United States",

}

Blaise, PD, De Wouters, RM & Abderrahim, HA 1994, Analysis of the venus out-of-core activation measurements using mcbend. in H Farrar, EP Lippincott, JG Williams & DW Vehar (eds), Reactor Dosimetry. ASTM Special Technical Publication, vol. STP 1228, American Society for Testing and Materials, pp. 323-332, 1993 - 8th ASTM-EURATOM symposium on reactor dosimetry, Vail, Colorado, United States, 1993-08-29. https://doi.org/10.1520/STP15125S

Analysis of the venus out-of-core activation measurements using mcbend. / Blaise, Patrick D.; De Wouters, Roger M.; Abderrahim, Hamid Ait.
Reactor Dosimetry. ed. / Harry Farrar; E. Parvin Lippincott; John G. Williams; David W. Vehar. American Society for Testing and Materials, 1994. p. 323-332 (ASTM Special Technical Publication; Vol. STP 1228).

Research output › peer-review

TY - GEN

T1 - Analysis of the venus out-of-core activation measurements using mcbend

AU - Blaise, Patrick D.

AU - De Wouters, Roger M.

AU - Abderrahim, Hamid Ait

PY - 1994

Y1 - 1994

N2 - The VENUS-I critical assembly simulates a U02-1oaded core and the internal structures from the core baffle to the neutron pad, in a generic 3-1oop plant. VENUS-2 contained mixed oxide PuO2 - UO2 fuel pins in the eight outer rows. Several out-of-core threshold activation rates (In-ll5, Np-237, Zn-64, AI-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 (σ). Further away from the core, the average C/E in the neutron pad from 13 measurements is 1.01 ± 0.08 (σ).

AB - The VENUS-I critical assembly simulates a U02-1oaded core and the internal structures from the core baffle to the neutron pad, in a generic 3-1oop plant. VENUS-2 contained mixed oxide PuO2 - UO2 fuel pins in the eight outer rows. Several out-of-core threshold activation rates (In-ll5, Np-237, Zn-64, AI-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 (σ). Further away from the core, the average C/E in the neutron pad from 13 measurements is 1.01 ± 0.08 (σ).

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DO - 10.1520/STP15125S

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PB - American Society for Testing and Materials

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