Quantification of the SCALE 6.1 eigenvalue uncertainty due to cross section uncertainties for exercise 1-1 of the IAEA CRP on HTGR uncertainties

V. V. Naicker; D. A. Maretele; F. Reitsma; F. Bostelmann; G. Strydom

Quantification of the SCALE 6.1 eigenvalue uncertainty due to cross section uncertainties for exercise 1-1 of the IAEA CRP on HTGR uncertainties

V. V. Naicker, D. A. Maretele, F. Reitsma, F. Bostelmann, G. Strydom

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

2 Scopus citations

Abstract

The IAEA Coordinated Research Project (CRP) on the HTGR Uncertainty Analysis in Modelling was launched in 2012 to study uncertainty propagation specifically in the HTGR analysis chain. The scope of the benchmark is to establish a well-defined set of problems to compare methods and tools in core simulation and thermal hydraulics analysis with a specific focus on uncertainty analysis and the propagation of these uncertainties through the different phases of the analysis. Both the prismatic and pebble bed designs of HTGRs are considered in the CRP but the focus in this paper is only on the prismatic block design, being represented by the MHTGR-350 test problem. The CRP is divided into a number of exercises. This paper reports the results of the first exercise, i.e. the uncertainty analysis of the multiplication factor based on the single cell. The single cell consists of the fuel compact and its graphite environment in the fuel block. The fuel compact in turn consists of TRISO particles embedded in a graphite matrix. Nominal models for the Monte Carlo code KENO-VI and the dis-crete-ordinate code NEWT of the SCALE 6.1 code package were built. Before propagating the uncertainties of nuclear data to uncertainties of output quantities, the basic models of KENO-VI and NEWT were studied for both convergence and computation time optimization. The uncertainties in the eigenvalue k_x of the homogenized fuel compact were calculated using the SCALE modules TSUNAMI-2D and TSUNAMI-3D together with the top contributions to the uncertainty in k_x by individual covariance matrices.

Original language	English
Title of host publication	Physics of Reactors 2016, PHYSOR 2016
Subtitle of host publication	Unifying Theory and Experiments in the 21st Century
Publisher	American Nuclear Society
Pages	2358-2370
Number of pages	13
ISBN (Electronic)	9781510825734
State	Published - 2016
Externally published	Yes
Event	Physics of Reactors 2016: Unifying Theory and Experiments in the 21st Century, PHYSOR 2016 - Sun Valley, United States Duration: May 1 2016 → May 5 2016

Publication series

Name	Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century
Volume	4

Conference

Conference	Physics of Reactors 2016: Unifying Theory and Experiments in the 21st Century, PHYSOR 2016
Country/Territory	United States
City	Sun Valley
Period	05/1/16 → 05/5/16

Funding

The NWU work is based upon research supported by the South African Research Chairs Initiative of the Department of Science and Technology and National Research Foundation, and also partially funded by the IAEA under Research Contract No 18703/RO. The GRS part of this work was supported by the German Federal Ministry for Economic Affairs and Energy. The INL contribution was prepared for the U.S. Department of Energy (Office of Nuclear Energy) under DOE Idaho Operations Office Contract DE-AC07-05ID14517.

Keywords

Convergence
HTGR
Optimization
Uncertainty quantification

Cite this

Naicker, V. V., Maretele, D. A., Reitsma, F., Bostelmann, F., & Strydom, G. (2016). Quantification of the SCALE 6.1 eigenvalue uncertainty due to cross section uncertainties for exercise 1-1 of the IAEA CRP on HTGR uncertainties. In Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century (pp. 2358-2370). (Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century; Vol. 4). American Nuclear Society.

Naicker, V. V. ; Maretele, D. A. ; Reitsma, F. et al. / Quantification of the SCALE 6.1 eigenvalue uncertainty due to cross section uncertainties for exercise 1-1 of the IAEA CRP on HTGR uncertainties. Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century. American Nuclear Society, 2016. pp. 2358-2370 (Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century).

@inproceedings{86e7db7c691344faafdd79d46d026532,

title = "Quantification of the SCALE 6.1 eigenvalue uncertainty due to cross section uncertainties for exercise 1-1 of the IAEA CRP on HTGR uncertainties",

abstract = "The IAEA Coordinated Research Project (CRP) on the HTGR Uncertainty Analysis in Modelling was launched in 2012 to study uncertainty propagation specifically in the HTGR analysis chain. The scope of the benchmark is to establish a well-defined set of problems to compare methods and tools in core simulation and thermal hydraulics analysis with a specific focus on uncertainty analysis and the propagation of these uncertainties through the different phases of the analysis. Both the prismatic and pebble bed designs of HTGRs are considered in the CRP but the focus in this paper is only on the prismatic block design, being represented by the MHTGR-350 test problem. The CRP is divided into a number of exercises. This paper reports the results of the first exercise, i.e. the uncertainty analysis of the multiplication factor based on the single cell. The single cell consists of the fuel compact and its graphite environment in the fuel block. The fuel compact in turn consists of TRISO particles embedded in a graphite matrix. Nominal models for the Monte Carlo code KENO-VI and the dis-crete-ordinate code NEWT of the SCALE 6.1 code package were built. Before propagating the uncertainties of nuclear data to uncertainties of output quantities, the basic models of KENO-VI and NEWT were studied for both convergence and computation time optimization. The uncertainties in the eigenvalue kx of the homogenized fuel compact were calculated using the SCALE modules TSUNAMI-2D and TSUNAMI-3D together with the top contributions to the uncertainty in kx by individual covariance matrices.",

keywords = "Convergence, HTGR, Optimization, Uncertainty quantification",

author = "Naicker, {V. V.} and Maretele, {D. A.} and F. Reitsma and F. Bostelmann and G. Strydom",

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series = "Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century",

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pages = "2358--2370",

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Naicker, VV, Maretele, DA, Reitsma, F, Bostelmann, F & Strydom, G 2016, Quantification of the SCALE 6.1 eigenvalue uncertainty due to cross section uncertainties for exercise 1-1 of the IAEA CRP on HTGR uncertainties. in Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century. Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, vol. 4, American Nuclear Society, pp. 2358-2370, Physics of Reactors 2016: Unifying Theory and Experiments in the 21st Century, PHYSOR 2016, Sun Valley, United States, 05/1/16.

Quantification of the SCALE 6.1 eigenvalue uncertainty due to cross section uncertainties for exercise 1-1 of the IAEA CRP on HTGR uncertainties. / Naicker, V. V.; Maretele, D. A.; Reitsma, F. et al.
Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century. American Nuclear Society, 2016. p. 2358-2370 (Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century; Vol. 4).

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

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AU - Maretele, D. A.

AU - Reitsma, F.

AU - Bostelmann, F.

AU - Strydom, G.

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N2 - The IAEA Coordinated Research Project (CRP) on the HTGR Uncertainty Analysis in Modelling was launched in 2012 to study uncertainty propagation specifically in the HTGR analysis chain. The scope of the benchmark is to establish a well-defined set of problems to compare methods and tools in core simulation and thermal hydraulics analysis with a specific focus on uncertainty analysis and the propagation of these uncertainties through the different phases of the analysis. Both the prismatic and pebble bed designs of HTGRs are considered in the CRP but the focus in this paper is only on the prismatic block design, being represented by the MHTGR-350 test problem. The CRP is divided into a number of exercises. This paper reports the results of the first exercise, i.e. the uncertainty analysis of the multiplication factor based on the single cell. The single cell consists of the fuel compact and its graphite environment in the fuel block. The fuel compact in turn consists of TRISO particles embedded in a graphite matrix. Nominal models for the Monte Carlo code KENO-VI and the dis-crete-ordinate code NEWT of the SCALE 6.1 code package were built. Before propagating the uncertainties of nuclear data to uncertainties of output quantities, the basic models of KENO-VI and NEWT were studied for both convergence and computation time optimization. The uncertainties in the eigenvalue kx of the homogenized fuel compact were calculated using the SCALE modules TSUNAMI-2D and TSUNAMI-3D together with the top contributions to the uncertainty in kx by individual covariance matrices.

AB - The IAEA Coordinated Research Project (CRP) on the HTGR Uncertainty Analysis in Modelling was launched in 2012 to study uncertainty propagation specifically in the HTGR analysis chain. The scope of the benchmark is to establish a well-defined set of problems to compare methods and tools in core simulation and thermal hydraulics analysis with a specific focus on uncertainty analysis and the propagation of these uncertainties through the different phases of the analysis. Both the prismatic and pebble bed designs of HTGRs are considered in the CRP but the focus in this paper is only on the prismatic block design, being represented by the MHTGR-350 test problem. The CRP is divided into a number of exercises. This paper reports the results of the first exercise, i.e. the uncertainty analysis of the multiplication factor based on the single cell. The single cell consists of the fuel compact and its graphite environment in the fuel block. The fuel compact in turn consists of TRISO particles embedded in a graphite matrix. Nominal models for the Monte Carlo code KENO-VI and the dis-crete-ordinate code NEWT of the SCALE 6.1 code package were built. Before propagating the uncertainties of nuclear data to uncertainties of output quantities, the basic models of KENO-VI and NEWT were studied for both convergence and computation time optimization. The uncertainties in the eigenvalue kx of the homogenized fuel compact were calculated using the SCALE modules TSUNAMI-2D and TSUNAMI-3D together with the top contributions to the uncertainty in kx by individual covariance matrices.

KW - Convergence

KW - HTGR

KW - Optimization

KW - Uncertainty quantification

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Naicker VV, Maretele DA, Reitsma F, Bostelmann F, Strydom G. Quantification of the SCALE 6.1 eigenvalue uncertainty due to cross section uncertainties for exercise 1-1 of the IAEA CRP on HTGR uncertainties. In Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century. American Nuclear Society. 2016. p. 2358-2370. (Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century).

Quantification of the SCALE 6.1 eigenvalue uncertainty due to cross section uncertainties for exercise 1-1 of the IAEA CRP on HTGR uncertainties

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