Validation of criticality safety calculations with SCALE 6.2

W. J. Marshall; D. Wiarda; C. Celik; B. T. Rearden; D. R. Wentz

Validation of criticality safety calculations with SCALE 6.2

W. J. Marshall, D. Wiarda, C. Celik, B. T. Rearden, D. R. Wentz

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

9 Scopus citations

Abstract

SCALE 6.2 provides numerous updates in nuclear data, nuclear data processing, and computational tools utilized in the criticality safety calculational sequences relative to SCALE 6.1. A new 252-group ENDF/B-VII.0 multigroup neutron library, improved ENDF/B-VII.0 continuous-energy data, as well as the previously deployed 238-group ENDF/B-VII.0 neutron library are included in SCALE 6.2 for criticality safety analysis. The performance of all three libraries for k_eff calculations is examined with a broad sampling of critical experiment models covering a range of fuels and moderators. Critical experiments from the International Handbook of Evaluated Criticality Safety Benchmark Experiments (IHECSBE) that are available in the SCALE Verified, Archived Library of Inputs and Data (VALID) are used in this validation effort. Over 300 cases are used in the validation of KENO V.a, and a more limited set of approximately 50 configurations is used for KENO-VI validation. Additionally, some KENO V.a cases are converted to KENO-VI models so that an equivalent set of experiments can be used to validate both codes. For continuous-energy calculations, SCALE 6.2 provides improved performance relative to SCALE 6.1 in most areas with notable improvements in fuel pin lattice cases, particularly those with mixed oxide fuel. Multigroup calculations with the 252-group library also demonstrate improved performance for fuel lattices, uranium (high and intermediate enrichment) and plutonium metal experiments, and plutonium solution systems. Overall, SCALE 6.2 provides equivalent or smaller biases than SCALE 6.1, and the two versions of KENO provide similar results on the same suite of problems.

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	747-759
Number of pages	13
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

KENO V.a
KENO-VI
SCALE
Validation

Cite this

Marshall, W. J., Wiarda, D., Celik, C., Rearden, B. T., & Wentz, D. R. (2013). Validation of criticality safety calculations with SCALE 6.2. In Topical Meeting Held by the ANS Nuclear Criticality Safety Division, NCSD 2013 - Criticality Safety in the Modern Era: Raising the Bar (pp. 747-759). (Topical Meeting Held by the ANS Nuclear Criticality Safety Division, NCSD 2013 - Criticality Safety in the Modern Era: Raising the Bar). American Nuclear Society.

Marshall, W. J. ; Wiarda, D. ; Celik, C. et al. / Validation of criticality safety calculations with SCALE 6.2. 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. 747-759 (Topical Meeting Held by the ANS Nuclear Criticality Safety Division, NCSD 2013 - Criticality Safety in the Modern Era: Raising the Bar).

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title = "Validation of criticality safety calculations with SCALE 6.2",

abstract = "SCALE 6.2 provides numerous updates in nuclear data, nuclear data processing, and computational tools utilized in the criticality safety calculational sequences relative to SCALE 6.1. A new 252-group ENDF/B-VII.0 multigroup neutron library, improved ENDF/B-VII.0 continuous-energy data, as well as the previously deployed 238-group ENDF/B-VII.0 neutron library are included in SCALE 6.2 for criticality safety analysis. The performance of all three libraries for keff calculations is examined with a broad sampling of critical experiment models covering a range of fuels and moderators. Critical experiments from the International Handbook of Evaluated Criticality Safety Benchmark Experiments (IHECSBE) that are available in the SCALE Verified, Archived Library of Inputs and Data (VALID) are used in this validation effort. Over 300 cases are used in the validation of KENO V.a, and a more limited set of approximately 50 configurations is used for KENO-VI validation. Additionally, some KENO V.a cases are converted to KENO-VI models so that an equivalent set of experiments can be used to validate both codes. For continuous-energy calculations, SCALE 6.2 provides improved performance relative to SCALE 6.1 in most areas with notable improvements in fuel pin lattice cases, particularly those with mixed oxide fuel. Multigroup calculations with the 252-group library also demonstrate improved performance for fuel lattices, uranium (high and intermediate enrichment) and plutonium metal experiments, and plutonium solution systems. Overall, SCALE 6.2 provides equivalent or smaller biases than SCALE 6.1, and the two versions of KENO provide similar results on the same suite of problems.",

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author = "Marshall, {W. J.} and D. Wiarda and C. Celik and Rearden, {B. T.} and Wentz, {D. R.}",

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publisher = "American Nuclear Society",

pages = "747--759",

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

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Marshall, WJ , Wiarda, D , Celik, C, Rearden, BT & Wentz, DR 2013, Validation of criticality safety calculations with SCALE 6.2. 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. 747-759, 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.

Validation of criticality safety calculations with SCALE 6.2. / Marshall, W. J.; Wiarda, D.; Celik, C. 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. 747-759 (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

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AU - Rearden, B. T.

AU - Wentz, D. R.

PY - 2013

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N2 - SCALE 6.2 provides numerous updates in nuclear data, nuclear data processing, and computational tools utilized in the criticality safety calculational sequences relative to SCALE 6.1. A new 252-group ENDF/B-VII.0 multigroup neutron library, improved ENDF/B-VII.0 continuous-energy data, as well as the previously deployed 238-group ENDF/B-VII.0 neutron library are included in SCALE 6.2 for criticality safety analysis. The performance of all three libraries for keff calculations is examined with a broad sampling of critical experiment models covering a range of fuels and moderators. Critical experiments from the International Handbook of Evaluated Criticality Safety Benchmark Experiments (IHECSBE) that are available in the SCALE Verified, Archived Library of Inputs and Data (VALID) are used in this validation effort. Over 300 cases are used in the validation of KENO V.a, and a more limited set of approximately 50 configurations is used for KENO-VI validation. Additionally, some KENO V.a cases are converted to KENO-VI models so that an equivalent set of experiments can be used to validate both codes. For continuous-energy calculations, SCALE 6.2 provides improved performance relative to SCALE 6.1 in most areas with notable improvements in fuel pin lattice cases, particularly those with mixed oxide fuel. Multigroup calculations with the 252-group library also demonstrate improved performance for fuel lattices, uranium (high and intermediate enrichment) and plutonium metal experiments, and plutonium solution systems. Overall, SCALE 6.2 provides equivalent or smaller biases than SCALE 6.1, and the two versions of KENO provide similar results on the same suite of problems.

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Marshall WJ , Wiarda D , Celik C, Rearden BT, Wentz DR. Validation of criticality safety calculations with SCALE 6.2. 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. 747-759. (Topical Meeting Held by the ANS Nuclear Criticality Safety Division, NCSD 2013 - Criticality Safety in the Modern Era: Raising the Bar).

Validation of criticality safety calculations with SCALE 6.2

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Publication series

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Keywords

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