Scale uncertainty quantification methodology for criticality safety analysis of used nuclear fuel

M. L. Williams; F. Havluj; D. Wiarda; M. Pigni; I. Gauld

Scale uncertainty quantification methodology for criticality safety analysis of used nuclear fuel

M. L. Williams, F. Havluj, D. Wiarda, M. Pigni, I. Gauld

Nuclear Data

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

5 Scopus citations

Abstract

A methodology based on stochastic sampling of input data covariances has been developed for uncertainty quantification with the SCALE code system. This provides the capability to determine uncertainties for a wide range of responses computed with any SCALE sequence. The methods used in the stochastic computation are discussed here for determining the uncertainty in the multiplication factor of used nuclear fuel (UNF), taking into account the impact of nuclear data uncertainties on the depletion calculations.

Original language	English
Title of host publication	Topical Meeting Held by the ANS Nuclear Criticality Safety Division, NCSD 2013 - Criticality Safety in the Modern Era
Subtitle of host publication	Raising the Bar
Publisher	American Nuclear Society
Pages	804-814
Number of pages	11
ISBN (Print)	9781629938165
State	Published - 2013
Event	Topical Meeting Held by the ANS Nuclear Criticality Safety Division - Criticality Safety in the Modern Era: Raising the Bar, NCSD 2013 - Wilmington, NC, United States Duration: Sep 29 2013 → Oct 3 2013

Publication series

Name	Topical Meeting Held by the ANS Nuclear Criticality Safety Division, NCSD 2013 - Criticality Safety in the Modern Era: Raising the Bar

Conference

Conference	Topical Meeting Held by the ANS Nuclear Criticality Safety Division - Criticality Safety in the Modern Era: Raising the Bar, NCSD 2013
Country/Territory	United States
City	Wilmington, NC
Period	09/29/13 → 10/3/13

Keywords

SCALE
Sampler
Stochastic sampling
Uncertainty analysis

Cite this

Williams, M. L., Havluj, F., Wiarda, D., Pigni, M., & Gauld, I. (2013). Scale uncertainty quantification methodology for criticality safety analysis of used nuclear fuel. In Topical Meeting Held by the ANS Nuclear Criticality Safety Division, NCSD 2013 - Criticality Safety in the Modern Era: Raising the Bar (pp. 804-814). (Topical Meeting Held by the ANS Nuclear Criticality Safety Division, NCSD 2013 - Criticality Safety in the Modern Era: Raising the Bar). American Nuclear Society.

Williams, M. L. ; Havluj, F. ; Wiarda, D. et al. / Scale uncertainty quantification methodology for criticality safety analysis of used nuclear fuel. Topical Meeting Held by the ANS Nuclear Criticality Safety Division, NCSD 2013 - Criticality Safety in the Modern Era: Raising the Bar. American Nuclear Society, 2013. pp. 804-814 (Topical Meeting Held by the ANS Nuclear Criticality Safety Division, NCSD 2013 - Criticality Safety in the Modern Era: Raising the Bar).

@inproceedings{aea87e0cb9b44c7b9c39e7566dcfbed1,

title = "Scale uncertainty quantification methodology for criticality safety analysis of used nuclear fuel",

abstract = "A methodology based on stochastic sampling of input data covariances has been developed for uncertainty quantification with the SCALE code system. This provides the capability to determine uncertainties for a wide range of responses computed with any SCALE sequence. The methods used in the stochastic computation are discussed here for determining the uncertainty in the multiplication factor of used nuclear fuel (UNF), taking into account the impact of nuclear data uncertainties on the depletion calculations.",

keywords = "SCALE, Sampler, Stochastic sampling, Uncertainty analysis",

author = "Williams, {M. L.} and F. Havluj and D. Wiarda and M. Pigni and I. Gauld",

year = "2013",

language = "English",

isbn = "9781629938165",

series = "Topical Meeting Held by the ANS Nuclear Criticality Safety Division, NCSD 2013 - Criticality Safety in the Modern Era: Raising the Bar",

publisher = "American Nuclear Society",

pages = "804--814",

booktitle = "Topical Meeting Held by the ANS Nuclear Criticality Safety Division, NCSD 2013 - Criticality Safety in the Modern Era",

note = "Topical Meeting Held by the ANS Nuclear Criticality Safety Division - Criticality Safety in the Modern Era: Raising the Bar, NCSD 2013 ; Conference date: 29-09-2013 Through 03-10-2013",

}

Williams, ML, Havluj, F, Wiarda, D , Pigni, M & Gauld, I 2013, Scale uncertainty quantification methodology for criticality safety analysis of used nuclear fuel. in Topical Meeting Held by the ANS Nuclear Criticality Safety Division, NCSD 2013 - Criticality Safety in the Modern Era: Raising the Bar. Topical Meeting Held by the ANS Nuclear Criticality Safety Division, NCSD 2013 - Criticality Safety in the Modern Era: Raising the Bar, American Nuclear Society, pp. 804-814, Topical Meeting Held by the ANS Nuclear Criticality Safety Division - Criticality Safety in the Modern Era: Raising the Bar, NCSD 2013, Wilmington, NC, United States, 09/29/13.

Scale uncertainty quantification methodology for criticality safety analysis of used nuclear fuel. / Williams, M. L.; Havluj, F.; Wiarda, D. et al.
Topical Meeting Held by the ANS Nuclear Criticality Safety Division, NCSD 2013 - Criticality Safety in the Modern Era: Raising the Bar. American Nuclear Society, 2013. p. 804-814 (Topical Meeting Held by the ANS Nuclear Criticality Safety Division, NCSD 2013 - Criticality Safety in the Modern Era: Raising the Bar).

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

TY - GEN

T1 - Scale uncertainty quantification methodology for criticality safety analysis of used nuclear fuel

AU - Williams, M. L.

AU - Havluj, F.

AU - Wiarda, D.

AU - Pigni, M.

AU - Gauld, I.

PY - 2013

Y1 - 2013

N2 - A methodology based on stochastic sampling of input data covariances has been developed for uncertainty quantification with the SCALE code system. This provides the capability to determine uncertainties for a wide range of responses computed with any SCALE sequence. The methods used in the stochastic computation are discussed here for determining the uncertainty in the multiplication factor of used nuclear fuel (UNF), taking into account the impact of nuclear data uncertainties on the depletion calculations.

AB - A methodology based on stochastic sampling of input data covariances has been developed for uncertainty quantification with the SCALE code system. This provides the capability to determine uncertainties for a wide range of responses computed with any SCALE sequence. The methods used in the stochastic computation are discussed here for determining the uncertainty in the multiplication factor of used nuclear fuel (UNF), taking into account the impact of nuclear data uncertainties on the depletion calculations.

KW - SCALE

KW - Sampler

KW - Stochastic sampling

KW - Uncertainty analysis

UR - http://www.scopus.com/inward/record.url?scp=84902239781&partnerID=8YFLogxK

M3 - Conference contribution

AN - SCOPUS:84902239781

SN - 9781629938165

T3 - Topical Meeting Held by the ANS Nuclear Criticality Safety Division, NCSD 2013 - Criticality Safety in the Modern Era: Raising the Bar

SP - 804

EP - 814

BT - Topical Meeting Held by the ANS Nuclear Criticality Safety Division, NCSD 2013 - Criticality Safety in the Modern Era

PB - American Nuclear Society

T2 - Topical Meeting Held by the ANS Nuclear Criticality Safety Division - Criticality Safety in the Modern Era: Raising the Bar, NCSD 2013

Y2 - 29 September 2013 through 3 October 2013

ER -

Williams ML, Havluj F, Wiarda D , Pigni M, Gauld I. Scale uncertainty quantification methodology for criticality safety analysis of used nuclear fuel. In Topical Meeting Held by the ANS Nuclear Criticality Safety Division, NCSD 2013 - Criticality Safety in the Modern Era: Raising the Bar. American Nuclear Society. 2013. p. 804-814. (Topical Meeting Held by the ANS Nuclear Criticality Safety Division, NCSD 2013 - Criticality Safety in the Modern Era: Raising the Bar).

Scale uncertainty quantification methodology for criticality safety analysis of used nuclear fuel

Abstract

Publication series

Conference

Keywords

Other files and links

Fingerprint

Cite this