Dynamic impact characteristics of KN-18 SNF transport cask - Part 1: An advanced numerical simulation and validation technique
- 1. Korea Nuclear Engineering and Service Corporation, 210-2 Yangjae-dong, Seocho-gu, Seoul 137-130 (Korea, Republic of)
- 2. Department of Aeronautical/Mechanical Design, Chungju National University, Jeungpyeong 368-903 (Korea, Republic of)
- 3. Department of Architectural Engineering, Chungnam National University, Daejeon 305-764 (Korea, Republic of)
Description
Domestic and international regulations for the transportation of radioactive materials strictly prescribe the design requirements for spent nuclear fuel (SNF) transport casks. According to the applicable codes, a transport cask must withstand a free-drop impact of 9 m onto an unyielding surface and a free-drop impact of 1 m onto a mild steel bar. However, the structural performance of a transport cask is not easy to evaluate precisely because the dynamic impact characteristics of the cask, which includes impact limiters to absorb the impact energy, are so complex. In this study, a more advanced and applicable numerical simulation method using the finite element (FE) method via the commercial FE code LS-DYNA is proposed and verified against the experimental results for a 1/3-scale model of the KN-18 SNF transport cask, recently developed in Korea. In addition, the detailed dynamic impact characteristics of the transport cask under free-drop conditions are investigated via the proposed numerical simulation method and actual drop tests to improve the accuracy and optimization of the SNF transport cask design.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2009.12.023Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2009.12.023;
- PII
- S0306-4549(09)00397-1;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 37
- Journal Issue
- 4
- Journal Page Range
- p. 546-559
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 41074080
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- ACCURACY; COMPUTERIZED SIMULATION; DESIGN; FINITE ELEMENT METHOD; INTERNATIONAL REGULATIONS; OPTIMIZATION; RADIOACTIVE MATERIALS; REPUBLIC OF KOREA; SCALE MODELS; SPENT FUEL CASKS; STEELS; TRANSPORT REGULATIONS; VALIDATION
- Descriptors DEC
- ALLOYS; ASIA; CALCULATION METHODS; CARBON ADDITIONS; CASKS; CONTAINERS; DEVELOPING COUNTRIES; IRON ALLOYS; IRON BASE ALLOYS; LAWS; MATERIALS; MATHEMATICAL SOLUTIONS; NUMERICAL SOLUTION; REGULATIONS; SIMULATION; STRUCTURAL MODELS; TESTING; TRANSITION ELEMENT ALLOYS
Optional Information
- Copyright
- Copyright (c) 2009 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.