Impact of nuclear data on sodium-cooled fast reactor calculations

Alexander Aures; Friederike Bostelmann; Winfried Zwermann; Kiril Velkov

doi:10.1051/epjconf/201611111003

Impact of nuclear data on sodium-cooled fast reactor calculations

Alexander Aures, Friederike Bostelmann, Winfried Zwermann, Kiril Velkov

Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) GGmbH

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

Abstract

Neutron transport and depletion calculations are performed in combination with various nuclear data libraries in order to assess the impact of nuclear data on safety-relevant parameters of sodium-cooled fast reactors. These calculations are supplemented by systematic uncertainty analyses with respect to nuclear data. Analysed quantities are the multiplication factor and nuclide densities as a function of burn-up and the Doppler and Na-void reactivity coefficients at begin of cycle. While ENDF/B-VII.0 / -VII.1 yield rather consistent results, larger discrepancies are observed between the JEFF libraries. While the newest evaluation, JEFF-3.2, agrees with the ENDF/B-VII libraries, the JEFF-3.1.2 library yields significant larger multiplication factors.

Original language	English
Title of host publication	WONDER 2015 - 4th International Workshop on Nuclear Data Evaluation for Reactor Applications
Editors	Olivier Serot
Publisher	EDP Sciences
ISBN (Electronic)	9782759819706
DOIs	https://doi.org/10.1051/epjconf/201611111003
State	Published - Mar 15 2016
Externally published	Yes
Event	4th International Workshop on Nuclear Data Evaluation for Reactor Applications, WONDER 2015 - Aix-en-Provence, France Duration: Oct 5 2015 → Oct 8 2015

Publication series

Name	EPJ Web of Conferences
Volume	111
ISSN (Print)	2101-6275
ISSN (Electronic)	2100-014X

Conference

Conference	4th International Workshop on Nuclear Data Evaluation for Reactor Applications, WONDER 2015
Country/Territory	France
City	Aix-en-Provence
Period	10/5/15 → 10/8/15

Bibliographical note

Publisher Copyright:
© Owned by the authors, published by EDP Sciences, 2016.

Access to Document

10.1051/epjconf/201611111003

Cite this

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title = "Impact of nuclear data on sodium-cooled fast reactor calculations",

abstract = "Neutron transport and depletion calculations are performed in combination with various nuclear data libraries in order to assess the impact of nuclear data on safety-relevant parameters of sodium-cooled fast reactors. These calculations are supplemented by systematic uncertainty analyses with respect to nuclear data. Analysed quantities are the multiplication factor and nuclide densities as a function of burn-up and the Doppler and Na-void reactivity coefficients at begin of cycle. While ENDF/B-VII.0 / -VII.1 yield rather consistent results, larger discrepancies are observed between the JEFF libraries. While the newest evaluation, JEFF-3.2, agrees with the ENDF/B-VII libraries, the JEFF-3.1.2 library yields significant larger multiplication factors.",

author = "Alexander Aures and Friederike Bostelmann and Winfried Zwermann and Kiril Velkov",

note = "Publisher Copyright: {\textcopyright} Owned by the authors, published by EDP Sciences, 2016.; 4th International Workshop on Nuclear Data Evaluation for Reactor Applications, WONDER 2015 ; Conference date: 05-10-2015 Through 08-10-2015",

year = "2016",

month = mar,

day = "15",

doi = "10.1051/epjconf/201611111003",

language = "English",

series = "EPJ Web of Conferences",

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Aures, A, Bostelmann, F, Zwermann, W & Velkov, K 2016, Impact of nuclear data on sodium-cooled fast reactor calculations. in O Serot (ed.), WONDER 2015 - 4th International Workshop on Nuclear Data Evaluation for Reactor Applications., 11003, EPJ Web of Conferences, vol. 111, EDP Sciences, 4th International Workshop on Nuclear Data Evaluation for Reactor Applications, WONDER 2015, Aix-en-Provence, France, 10/5/15. https://doi.org/10.1051/epjconf/201611111003

Impact of nuclear data on sodium-cooled fast reactor calculations. / Aures, Alexander; Bostelmann, Friederike; Zwermann, Winfried et al.
WONDER 2015 - 4th International Workshop on Nuclear Data Evaluation for Reactor Applications. ed. / Olivier Serot. EDP Sciences, 2016. 11003 (EPJ Web of Conferences; Vol. 111).

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

TY - GEN

T1 - Impact of nuclear data on sodium-cooled fast reactor calculations

AU - Aures, Alexander

AU - Bostelmann, Friederike

AU - Zwermann, Winfried

AU - Velkov, Kiril

PY - 2016/3/15

Y1 - 2016/3/15

N2 - Neutron transport and depletion calculations are performed in combination with various nuclear data libraries in order to assess the impact of nuclear data on safety-relevant parameters of sodium-cooled fast reactors. These calculations are supplemented by systematic uncertainty analyses with respect to nuclear data. Analysed quantities are the multiplication factor and nuclide densities as a function of burn-up and the Doppler and Na-void reactivity coefficients at begin of cycle. While ENDF/B-VII.0 / -VII.1 yield rather consistent results, larger discrepancies are observed between the JEFF libraries. While the newest evaluation, JEFF-3.2, agrees with the ENDF/B-VII libraries, the JEFF-3.1.2 library yields significant larger multiplication factors.

AB - Neutron transport and depletion calculations are performed in combination with various nuclear data libraries in order to assess the impact of nuclear data on safety-relevant parameters of sodium-cooled fast reactors. These calculations are supplemented by systematic uncertainty analyses with respect to nuclear data. Analysed quantities are the multiplication factor and nuclide densities as a function of burn-up and the Doppler and Na-void reactivity coefficients at begin of cycle. While ENDF/B-VII.0 / -VII.1 yield rather consistent results, larger discrepancies are observed between the JEFF libraries. While the newest evaluation, JEFF-3.2, agrees with the ENDF/B-VII libraries, the JEFF-3.1.2 library yields significant larger multiplication factors.

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M3 - Conference contribution

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T3 - EPJ Web of Conferences

BT - WONDER 2015 - 4th International Workshop on Nuclear Data Evaluation for Reactor Applications

A2 - Serot, Olivier

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T2 - 4th International Workshop on Nuclear Data Evaluation for Reactor Applications, WONDER 2015

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Impact of nuclear data on sodium-cooled fast reactor calculations

Abstract

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