Probabilistic risk assessment of drop accident of cask with o-ring seal during on-site spent nuclear fuel transportation

Jaehyun Ham; Belal Al Momani; Robby Christian; Hyun Gook Kang

Probabilistic risk assessment of drop accident of cask with o-ring seal during on-site spent nuclear fuel transportation

Jaehyun Ham
, Belal Al Momani
, Robby Christian
, Hyun Gook Kang

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

Abstract

PRA (Probabilistic Risk Assessment) of cask drop accident during on-site SNF (Spent Nuclear Fuel) transportation between SFP (Spent Fuel Pool) and wharf in NPP site was done in this research. Modified process of cask storage system was used. Based on modified process with height and state of cask, drop accident scenarios were invented. Bolted metal cask is selected as a target cask, which is composed of four parts: 21 fuel assemblies, cask body, 2 cask lids, and 2 impact limiters. Based on the results of FDR (Fuel Damage Ratio) and Release Fraction from cask to environment (RF_c-e) from the simulation of ABAQUS, source term from cask drop accident was calculated. For all stages, side drop was applied. With the source term, risk to each person in LPZ (Low Population Zone) was calculated by Hotspot code. The total risk in LPZ with 45,000 MWD/MTU burn-up SNFs was calculated as 1.906E-06 man-person/transport for rubber o-ring case, and 8.413E-06 for metal o-ring case.

Original language	English
Title of host publication	Proceedings - 22nd ISSAT International Conference on Reliability and Quality in Design
Editors	Hoang Pham
Publisher	International Society of Science and Applied Technologies
Pages	353-356
Number of pages	4
ISBN (Electronic)	9780991057634
State	Published - 2016
Externally published	Yes
Event	22nd ISSAT International Conference on Reliability and Quality in Design - Los Angeles, United States Duration: 4 Aug 2016 → 6 Aug 2016

Publication series

Name	Proceedings - 22nd ISSAT International Conference on Reliability and Quality in Design

Conference

Conference	22nd ISSAT International Conference on Reliability and Quality in Design
Country/Territory	United States
City	Los Angeles
Period	4/08/16 → 6/08/16

Bibliographical note

Publisher Copyright:
© 2016, International Society of Science and Applied Technologies. All rights reserved.

UN SDGs

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

SDG 12 Responsible Consumption and Production

Keywords

Cask drop accident
On-site transportation
Probabilistic risk assessment
Spent nuclear fuel

ASJC Scopus subject areas

Safety, Risk, Reliability and Quality

Cite this

Ham, J., Al Momani, B., Christian, R., & Kang, H. G. (2016). Probabilistic risk assessment of drop accident of cask with o-ring seal during on-site spent nuclear fuel transportation. In H. Pham (Ed.), Proceedings - 22nd ISSAT International Conference on Reliability and Quality in Design (pp. 353-356). (Proceedings - 22nd ISSAT International Conference on Reliability and Quality in Design). International Society of Science and Applied Technologies.

Ham, Jaehyun ; Al Momani, Belal ; Christian, Robby et al. / Probabilistic risk assessment of drop accident of cask with o-ring seal during on-site spent nuclear fuel transportation. Proceedings - 22nd ISSAT International Conference on Reliability and Quality in Design. editor / Hoang Pham. International Society of Science and Applied Technologies, 2016. pp. 353-356 (Proceedings - 22nd ISSAT International Conference on Reliability and Quality in Design).

@inproceedings{7c64fd276f1148fc971c1ea30d90191c,

title = "Probabilistic risk assessment of drop accident of cask with o-ring seal during on-site spent nuclear fuel transportation",

abstract = "PRA (Probabilistic Risk Assessment) of cask drop accident during on-site SNF (Spent Nuclear Fuel) transportation between SFP (Spent Fuel Pool) and wharf in NPP site was done in this research. Modified process of cask storage system was used. Based on modified process with height and state of cask, drop accident scenarios were invented. Bolted metal cask is selected as a target cask, which is composed of four parts: 21 fuel assemblies, cask body, 2 cask lids, and 2 impact limiters. Based on the results of FDR (Fuel Damage Ratio) and Release Fraction from cask to environment (RFc-e) from the simulation of ABAQUS, source term from cask drop accident was calculated. For all stages, side drop was applied. With the source term, risk to each person in LPZ (Low Population Zone) was calculated by Hotspot code. The total risk in LPZ with 45,000 MWD/MTU burn-up SNFs was calculated as 1.906E-06 man-person/transport for rubber o-ring case, and 8.413E-06 for metal o-ring case.",

keywords = "Cask drop accident, On-site transportation, Probabilistic risk assessment, Spent nuclear fuel",

author = "Jaehyun Ham and \{Al Momani\}, Belal and Robby Christian and Kang, \{Hyun Gook\}",

note = "Publisher Copyright: {\textcopyright} 2016, International Society of Science and Applied Technologies. All rights reserved.; 22nd ISSAT International Conference on Reliability and Quality in Design ; Conference date: 04-08-2016 Through 06-08-2016",

year = "2016",

language = "English",

series = "Proceedings - 22nd ISSAT International Conference on Reliability and Quality in Design",

publisher = "International Society of Science and Applied Technologies",

pages = "353--356",

editor = "Hoang Pham",

booktitle = "Proceedings - 22nd ISSAT International Conference on Reliability and Quality in Design",

}

Ham, J, Al Momani, B, Christian, R & Kang, HG 2016, Probabilistic risk assessment of drop accident of cask with o-ring seal during on-site spent nuclear fuel transportation. in H Pham (ed.), Proceedings - 22nd ISSAT International Conference on Reliability and Quality in Design. Proceedings - 22nd ISSAT International Conference on Reliability and Quality in Design, International Society of Science and Applied Technologies, pp. 353-356, 22nd ISSAT International Conference on Reliability and Quality in Design, Los Angeles, United States, 4/08/16.

Probabilistic risk assessment of drop accident of cask with o-ring seal during on-site spent nuclear fuel transportation. / Ham, Jaehyun; Al Momani, Belal; Christian, Robby et al.
Proceedings - 22nd ISSAT International Conference on Reliability and Quality in Design. ed. / Hoang Pham. International Society of Science and Applied Technologies, 2016. p. 353-356 (Proceedings - 22nd ISSAT International Conference on Reliability and Quality in Design).

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

TY - GEN

T1 - Probabilistic risk assessment of drop accident of cask with o-ring seal during on-site spent nuclear fuel transportation

AU - Ham, Jaehyun

AU - Al Momani, Belal

AU - Christian, Robby

AU - Kang, Hyun Gook

PY - 2016

Y1 - 2016

N2 - PRA (Probabilistic Risk Assessment) of cask drop accident during on-site SNF (Spent Nuclear Fuel) transportation between SFP (Spent Fuel Pool) and wharf in NPP site was done in this research. Modified process of cask storage system was used. Based on modified process with height and state of cask, drop accident scenarios were invented. Bolted metal cask is selected as a target cask, which is composed of four parts: 21 fuel assemblies, cask body, 2 cask lids, and 2 impact limiters. Based on the results of FDR (Fuel Damage Ratio) and Release Fraction from cask to environment (RFc-e) from the simulation of ABAQUS, source term from cask drop accident was calculated. For all stages, side drop was applied. With the source term, risk to each person in LPZ (Low Population Zone) was calculated by Hotspot code. The total risk in LPZ with 45,000 MWD/MTU burn-up SNFs was calculated as 1.906E-06 man-person/transport for rubber o-ring case, and 8.413E-06 for metal o-ring case.

AB - PRA (Probabilistic Risk Assessment) of cask drop accident during on-site SNF (Spent Nuclear Fuel) transportation between SFP (Spent Fuel Pool) and wharf in NPP site was done in this research. Modified process of cask storage system was used. Based on modified process with height and state of cask, drop accident scenarios were invented. Bolted metal cask is selected as a target cask, which is composed of four parts: 21 fuel assemblies, cask body, 2 cask lids, and 2 impact limiters. Based on the results of FDR (Fuel Damage Ratio) and Release Fraction from cask to environment (RFc-e) from the simulation of ABAQUS, source term from cask drop accident was calculated. For all stages, side drop was applied. With the source term, risk to each person in LPZ (Low Population Zone) was calculated by Hotspot code. The total risk in LPZ with 45,000 MWD/MTU burn-up SNFs was calculated as 1.906E-06 man-person/transport for rubber o-ring case, and 8.413E-06 for metal o-ring case.

KW - Cask drop accident

KW - On-site transportation

KW - Probabilistic risk assessment

KW - Spent nuclear fuel

UR - https://www.scopus.com/pages/publications/84992110681

M3 - Conference contribution

AN - SCOPUS:84992110681

T3 - Proceedings - 22nd ISSAT International Conference on Reliability and Quality in Design

SP - 353

EP - 356

BT - Proceedings - 22nd ISSAT International Conference on Reliability and Quality in Design

A2 - Pham, Hoang

PB - International Society of Science and Applied Technologies

T2 - 22nd ISSAT International Conference on Reliability and Quality in Design

Y2 - 4 August 2016 through 6 August 2016

ER -

Ham J, Al Momani B, Christian R, Kang HG. Probabilistic risk assessment of drop accident of cask with o-ring seal during on-site spent nuclear fuel transportation. In Pham H, editor, Proceedings - 22nd ISSAT International Conference on Reliability and Quality in Design. International Society of Science and Applied Technologies. 2016. p. 353-356. (Proceedings - 22nd ISSAT International Conference on Reliability and Quality in Design).

Probabilistic risk assessment of drop accident of cask with o-ring seal during on-site spent nuclear fuel transportation

Abstract

Publication series

Conference

Bibliographical note

UN SDGs

Keywords

ASJC Scopus subject areas

Fingerprint

Cite this