Shielding benchmark calculations of selected spent fuel storage cask experiments

B. L. Broadhead; J. S. Tang; C. V. Parks; H. Taniuchi

Shielding benchmark calculations of selected spent fuel storage cask experiments

B. L. Broadhead, J. S. Tang, C. V. Parks, H. Taniuchi

Controls Integration

Oak Ridge National Laboratory

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

Abstract

This paper describes the application of the three-dimensional Monte Carlo code MORSE-SGC, as implemented in the SCALE system calculational sequence SAS4, to the analysis of a series of benchmark spent fuel storage cask measurements performed at the Idaho National Engineering Laboratory. A total of five storage cask problems were analyzed to determine the expected accuracies of computational analyses using well-established Monte Carlo codes. The results presented herein represent the current status of the work.

Original language	English
Title of host publication	High Level Radioactive Waste Management
Publisher	Publ by ASCE
Pages	1377-1382
Number of pages	6
ISBN (Print)	0872629503
State	Published - 1993
Event	Proceedings of the 4th Annual International Conference on High Level Radioactive Waste Management - Las Vegas, NV, USA Duration: Apr 26 1993 → Apr 30 1993

Publication series

Name	High Level Radioactive Waste Management

Conference

Conference	Proceedings of the 4th Annual International Conference on High Level Radioactive Waste Management
City	Las Vegas, NV, USA
Period	04/26/93 → 04/30/93

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

Cite this

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title = "Shielding benchmark calculations of selected spent fuel storage cask experiments",

abstract = "This paper describes the application of the three-dimensional Monte Carlo code MORSE-SGC, as implemented in the SCALE system calculational sequence SAS4, to the analysis of a series of benchmark spent fuel storage cask measurements performed at the Idaho National Engineering Laboratory. A total of five storage cask problems were analyzed to determine the expected accuracies of computational analyses using well-established Monte Carlo codes. The results presented herein represent the current status of the work.",

author = "Broadhead, {B. L.} and Tang, {J. S.} and Parks, {C. V.} and H. Taniuchi",

year = "1993",

language = "English",

isbn = "0872629503",

series = "High Level Radioactive Waste Management",

publisher = "Publ by ASCE",

pages = "1377--1382",

booktitle = "High Level Radioactive Waste Management",

note = "Proceedings of the 4th Annual International Conference on High Level Radioactive Waste Management ; Conference date: 26-04-1993 Through 30-04-1993",

}

Broadhead, BL, Tang, JS, Parks, CV & Taniuchi, H 1993, Shielding benchmark calculations of selected spent fuel storage cask experiments. in High Level Radioactive Waste Management. High Level Radioactive Waste Management, Publ by ASCE, pp. 1377-1382, Proceedings of the 4th Annual International Conference on High Level Radioactive Waste Management, Las Vegas, NV, USA, 04/26/93.

TY - GEN

T1 - Shielding benchmark calculations of selected spent fuel storage cask experiments

AU - Broadhead, B. L.

AU - Tang, J. S.

AU - Parks, C. V.

AU - Taniuchi, H.

PY - 1993

Y1 - 1993

N2 - This paper describes the application of the three-dimensional Monte Carlo code MORSE-SGC, as implemented in the SCALE system calculational sequence SAS4, to the analysis of a series of benchmark spent fuel storage cask measurements performed at the Idaho National Engineering Laboratory. A total of five storage cask problems were analyzed to determine the expected accuracies of computational analyses using well-established Monte Carlo codes. The results presented herein represent the current status of the work.

AB - This paper describes the application of the three-dimensional Monte Carlo code MORSE-SGC, as implemented in the SCALE system calculational sequence SAS4, to the analysis of a series of benchmark spent fuel storage cask measurements performed at the Idaho National Engineering Laboratory. A total of five storage cask problems were analyzed to determine the expected accuracies of computational analyses using well-established Monte Carlo codes. The results presented herein represent the current status of the work.

UR - http://www.scopus.com/inward/record.url?scp=0027188475&partnerID=8YFLogxK

M3 - Conference contribution

AN - SCOPUS:0027188475

SN - 0872629503

T3 - High Level Radioactive Waste Management

SP - 1377

EP - 1382

BT - High Level Radioactive Waste Management

PB - Publ by ASCE

T2 - Proceedings of the 4th Annual International Conference on High Level Radioactive Waste Management

Y2 - 26 April 1993 through 30 April 1993

ER -

Shielding benchmark calculations of selected spent fuel storage cask experiments

Abstract

Publication series

Conference

UN SDGs

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