Use of ENDF/B-VI.5 and JEF-2.2 evaluations for the 3-D venus-2 benchmark

Nadia Messaoudi; Hamid Aït Abderrahim

Use of ENDF/B-VI.5 and JEF-2.2 evaluations for the 3-D venus-2 benchmark

Research output › peer-review

Abstract

The OECD/NEA launched a benchmark based on three-dimensional VENUS-2 experimental results. In the previous two-dimensional benchmark, even though the results were generally in good agreement with the experimental data, all the calculations overestimated pin powers of MOX rods and slightly underestimated those of UO₂ rods. Therefore, the objective of this benchmark is to investigate more thoroughly calculation methods (codes and nuclear data) for MOX-fuelled core. For this purpose, SCK•CEN (the Belgian nuclear research centre, at Mol) released to the OECD/NEA the three-dimensional VENUS-2 MOX core experimental data in October 2000. The experimental results for this benchmark mainly consist of the measured fission rate distributions (by γ-scanning) of six fuel rods at 21 different axial points and the multiplication factor. This paper presents the results obtained by using the Monte Carlo code MCNP (version 4C) with two different nuclear data evaluations: ENDF/B-VI (release 5) and JEF-2.2. The sensitivity of some requested results (K_∞ of the 3 different VENUS-2 fuel cells, axial pin power distributions of six fuel rods, and K_eff) to the nuclear data used is analysed.

Original language	English
Title of host publication	Proceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology
Subtitle of host publication	Reactor Physics, Safety and High-Performance Computing - The ANS 2002 RPD Topical Meeting
Publisher	American Nuclear Society
ISBN (Electronic)	0894486721, 9780894486722
State	Published - 2002
Event	2002 International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing, PHYSOR 2002 - Seoul Duration: 7 Oct 2002 → 10 Oct 2002

Publication series

Name	Proceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing - The ANS 2002 RPD Topical Meeting

Conference

Conference	2002 International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing, PHYSOR 2002
Country/Territory	Korea, Republic of
City	Seoul
Period	2002-10-07 → 2002-10-10

ASJC Scopus subject areas

Nuclear Energy and Engineering
Nuclear and High Energy Physics
Radiation
Safety, Risk, Reliability and Quality

Cite this

Messaoudi, N., & Abderrahim, H. A. (2002). Use of ENDF/B-VI.5 and JEF-2.2 evaluations for the 3-D venus-2 benchmark. In Proceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing - The ANS 2002 RPD Topical Meeting (Proceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing - The ANS 2002 RPD Topical Meeting). American Nuclear Society.

Messaoudi, Nadia ; Abderrahim, Hamid Aït. / Use of ENDF/B-VI.5 and JEF-2.2 evaluations for the 3-D venus-2 benchmark. Proceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing - The ANS 2002 RPD Topical Meeting. American Nuclear Society, 2002. (Proceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing - The ANS 2002 RPD Topical Meeting).

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abstract = "The OECD/NEA launched a benchmark based on three-dimensional VENUS-2 experimental results. In the previous two-dimensional benchmark, even though the results were generally in good agreement with the experimental data, all the calculations overestimated pin powers of MOX rods and slightly underestimated those of UO2 rods. Therefore, the objective of this benchmark is to investigate more thoroughly calculation methods (codes and nuclear data) for MOX-fuelled core. For this purpose, SCK•CEN (the Belgian nuclear research centre, at Mol) released to the OECD/NEA the three-dimensional VENUS-2 MOX core experimental data in October 2000. The experimental results for this benchmark mainly consist of the measured fission rate distributions (by γ-scanning) of six fuel rods at 21 different axial points and the multiplication factor. This paper presents the results obtained by using the Monte Carlo code MCNP (version 4C) with two different nuclear data evaluations: ENDF/B-VI (release 5) and JEF-2.2. The sensitivity of some requested results (K∞ of the 3 different VENUS-2 fuel cells, axial pin power distributions of six fuel rods, and Keff) to the nuclear data used is analysed.",

author = "Nadia Messaoudi and Abderrahim, {Hamid A{\"i}t}",

note = "Publisher Copyright: {\textcopyright} PHYSOR 2002.All right reserved.; 2002 International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing, PHYSOR 2002 ; Conference date: 07-10-2002 Through 10-10-2002",

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series = "Proceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing - The ANS 2002 RPD Topical Meeting",

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Messaoudi, N & Abderrahim, HA 2002, Use of ENDF/B-VI.5 and JEF-2.2 evaluations for the 3-D venus-2 benchmark. in Proceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing - The ANS 2002 RPD Topical Meeting. Proceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing - The ANS 2002 RPD Topical Meeting, American Nuclear Society, 2002 International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing, PHYSOR 2002, Seoul, Korea, Republic of, 2002-10-07.

Use of ENDF/B-VI.5 and JEF-2.2 evaluations for the 3-D venus-2 benchmark. / Messaoudi, Nadia ; Abderrahim, Hamid Aït.
Proceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing - The ANS 2002 RPD Topical Meeting. American Nuclear Society, 2002. (Proceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing - The ANS 2002 RPD Topical Meeting).

Research output › peer-review

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T1 - Use of ENDF/B-VI.5 and JEF-2.2 evaluations for the 3-D venus-2 benchmark

AU - Messaoudi, Nadia

AU - Abderrahim, Hamid Aït

PY - 2002

Y1 - 2002

N2 - The OECD/NEA launched a benchmark based on three-dimensional VENUS-2 experimental results. In the previous two-dimensional benchmark, even though the results were generally in good agreement with the experimental data, all the calculations overestimated pin powers of MOX rods and slightly underestimated those of UO2 rods. Therefore, the objective of this benchmark is to investigate more thoroughly calculation methods (codes and nuclear data) for MOX-fuelled core. For this purpose, SCK•CEN (the Belgian nuclear research centre, at Mol) released to the OECD/NEA the three-dimensional VENUS-2 MOX core experimental data in October 2000. The experimental results for this benchmark mainly consist of the measured fission rate distributions (by γ-scanning) of six fuel rods at 21 different axial points and the multiplication factor. This paper presents the results obtained by using the Monte Carlo code MCNP (version 4C) with two different nuclear data evaluations: ENDF/B-VI (release 5) and JEF-2.2. The sensitivity of some requested results (K∞ of the 3 different VENUS-2 fuel cells, axial pin power distributions of six fuel rods, and Keff) to the nuclear data used is analysed.

AB - The OECD/NEA launched a benchmark based on three-dimensional VENUS-2 experimental results. In the previous two-dimensional benchmark, even though the results were generally in good agreement with the experimental data, all the calculations overestimated pin powers of MOX rods and slightly underestimated those of UO2 rods. Therefore, the objective of this benchmark is to investigate more thoroughly calculation methods (codes and nuclear data) for MOX-fuelled core. For this purpose, SCK•CEN (the Belgian nuclear research centre, at Mol) released to the OECD/NEA the three-dimensional VENUS-2 MOX core experimental data in October 2000. The experimental results for this benchmark mainly consist of the measured fission rate distributions (by γ-scanning) of six fuel rods at 21 different axial points and the multiplication factor. This paper presents the results obtained by using the Monte Carlo code MCNP (version 4C) with two different nuclear data evaluations: ENDF/B-VI (release 5) and JEF-2.2. The sensitivity of some requested results (K∞ of the 3 different VENUS-2 fuel cells, axial pin power distributions of six fuel rods, and Keff) to the nuclear data used is analysed.

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M3 - In-proceedings paper

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T3 - Proceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing - The ANS 2002 RPD Topical Meeting

BT - Proceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology

PB - American Nuclear Society

T2 - 2002 International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing, PHYSOR 2002

Y2 - 7 October 2002 through 10 October 2002

ER -

Messaoudi N , Abderrahim HA. Use of ENDF/B-VI.5 and JEF-2.2 evaluations for the 3-D venus-2 benchmark. In Proceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing - The ANS 2002 RPD Topical Meeting. American Nuclear Society. 2002. (Proceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing - The ANS 2002 RPD Topical Meeting).