Improved MOX fuel calculations using new Pu-239, Am-241 and Pu-240 evaluations

G. Noguere; O. Bouland; D. Bernard; P. Leconte; P. Blaise; Y. Peneliau; J. F. Vidal; C. De Saint Jean; L. Leal; P. Schillebeeckx; S. Kopecky; C. Lampoudis

doi:10.1051/epjconf/20134205005

Improved MOX fuel calculations using new Pu-239, Am-241 and Pu-240 evaluations

G. Noguere
, O. Bouland
, D. Bernard
, P. Leconte
, P. Blaise
, Y. Peneliau
, J. F. Vidal
, C. De Saint Jean
, L. Leal
, P. Schillebeeckx
, S. Kopecky
, C. Lampoudis

Criticality Safety Analysis and Research

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

2 Scopus citations

Abstract

Several studies based on the JEFF-3.1.1 nuclear data library show a systematic overestimation of the critical keff for core configurations of MOX fuel assemblies. The present work investigates possible improvements of the C/E results by using new evaluations for Am-241, Pu-239 and Pu-240.

Original language	English
Title of host publication	WONDER 2012 - 3rd International Workshop on Nuclear Data Evaluation for Reactor Applications
DOIs	https://doi.org/10.1051/epjconf/20134205005
State	Published - 2013
Event	3rd International Workshop on Nuclear Data Evaluation for Reactor Applications, WONDER 2012 - Aix-en-Provence, France Duration: Sep 25 2012 → Sep 28 2012

Publication series

Name	EPJ Web of Conferences
Volume	42
ISSN (Print)	2101-6275
ISSN (Electronic)	2100-014X

Conference

Conference	3rd International Workshop on Nuclear Data Evaluation for Reactor Applications, WONDER 2012
Country/Territory	France
City	Aix-en-Provence
Period	09/25/12 → 09/28/12

Access to Document

10.1051/epjconf/20134205005

Cite this

Noguere, G., Bouland, O., Bernard, D., Leconte, P., Blaise, P., Peneliau, Y., Vidal, J. F., De Saint Jean, C., Leal, L., Schillebeeckx, P., Kopecky, S., & Lampoudis, C. (2013). Improved MOX fuel calculations using new Pu-239, Am-241 and Pu-240 evaluations. In WONDER 2012 - 3rd International Workshop on Nuclear Data Evaluation for Reactor Applications Article 05005 (EPJ Web of Conferences; Vol. 42). https://doi.org/10.1051/epjconf/20134205005

@inproceedings{61447204ecb04d329e32830a8023303c,

title = "Improved MOX fuel calculations using new Pu-239, Am-241 and Pu-240 evaluations",

abstract = "Several studies based on the JEFF-3.1.1 nuclear data library show a systematic overestimation of the critical keff for core configurations of MOX fuel assemblies. The present work investigates possible improvements of the C/E results by using new evaluations for Am-241, Pu-239 and Pu-240.",

author = "G. Noguere and O. Bouland and D. Bernard and P. Leconte and P. Blaise and Y. Peneliau and Vidal, \{J. F.\} and \{De Saint Jean\}, C. and L. Leal and P. Schillebeeckx and S. Kopecky and C. Lampoudis",

year = "2013",

doi = "10.1051/epjconf/20134205005",

language = "English",

isbn = "9782759809615",

series = "EPJ Web of Conferences",

booktitle = "WONDER 2012 - 3rd International Workshop on Nuclear Data Evaluation for Reactor Applications",

note = "3rd International Workshop on Nuclear Data Evaluation for Reactor Applications, WONDER 2012 ; Conference date: 25-09-2012 Through 28-09-2012",

}

Noguere, G, Bouland, O, Bernard, D, Leconte, P, Blaise, P, Peneliau, Y, Vidal, JF, De Saint Jean, C, Leal, L, Schillebeeckx, P, Kopecky, S & Lampoudis, C 2013, Improved MOX fuel calculations using new Pu-239, Am-241 and Pu-240 evaluations. in WONDER 2012 - 3rd International Workshop on Nuclear Data Evaluation for Reactor Applications., 05005, EPJ Web of Conferences, vol. 42, 3rd International Workshop on Nuclear Data Evaluation for Reactor Applications, WONDER 2012, Aix-en-Provence, France, 09/25/12. https://doi.org/10.1051/epjconf/20134205005

Improved MOX fuel calculations using new Pu-239, Am-241 and Pu-240 evaluations. / Noguere, G.; Bouland, O.; Bernard, D. et al.
WONDER 2012 - 3rd International Workshop on Nuclear Data Evaluation for Reactor Applications. 2013. 05005 (EPJ Web of Conferences; Vol. 42).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

TY - GEN

T1 - Improved MOX fuel calculations using new Pu-239, Am-241 and Pu-240 evaluations

AU - Noguere, G.

AU - Bouland, O.

AU - Bernard, D.

AU - Leconte, P.

AU - Blaise, P.

AU - Peneliau, Y.

AU - Vidal, J. F.

AU - De Saint Jean, C.

AU - Leal, L.

AU - Schillebeeckx, P.

AU - Kopecky, S.

AU - Lampoudis, C.

PY - 2013

Y1 - 2013

N2 - Several studies based on the JEFF-3.1.1 nuclear data library show a systematic overestimation of the critical keff for core configurations of MOX fuel assemblies. The present work investigates possible improvements of the C/E results by using new evaluations for Am-241, Pu-239 and Pu-240.

AB - Several studies based on the JEFF-3.1.1 nuclear data library show a systematic overestimation of the critical keff for core configurations of MOX fuel assemblies. The present work investigates possible improvements of the C/E results by using new evaluations for Am-241, Pu-239 and Pu-240.

UR - https://www.scopus.com/pages/publications/84875753440

U2 - 10.1051/epjconf/20134205005

DO - 10.1051/epjconf/20134205005

M3 - Conference contribution

AN - SCOPUS:84875753440

SN - 9782759809615

T3 - EPJ Web of Conferences

BT - WONDER 2012 - 3rd International Workshop on Nuclear Data Evaluation for Reactor Applications

T2 - 3rd International Workshop on Nuclear Data Evaluation for Reactor Applications, WONDER 2012

Y2 - 25 September 2012 through 28 September 2012

ER -

Improved MOX fuel calculations using new Pu-239, Am-241 and Pu-240 evaluations

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