[논문]Stress-based vs. Strain-based safety evaluations of spent nuclear fuel transport casks in energy-limited events

Kim, Seung-Pil; Kim, Jeongho; Sohn, Dongseong; Kwon, Hyukjoo; Shin, Myoungsu

doi:10.1016/j.nucengdes.2019.110324

Stress-based vs. Strain-based safety evaluations of spent nuclear fuel transport casks in energy-limited events

Nuclear engineering and design : an international journal devoted to the thermal, mechanical and structural problems of nuclear energy, v.355, 2019년, pp.110324 -

Kim, Seung-Pil (School of Urban and Environmental Engineering, Ulsan National Institute of Science and Technology (UNIST)) , Kim, Jeongho (Department of Civil and Environmental Engineering, University of Connecticut) , Sohn, Dongseong (HANSCO Co.) , Kwon, Hyukjoo (HANSCO Co.) , Shin, Myoungsu (School of Urban and Environmental Engineering, Ulsan National Institute of Science and Technology (UNIST))

Abstract ▼ AI-Helper

Abstract The stress-based criteria specified in ASME Section III (American Society of Mechanical Engineers, 2010) have long been used to evaluate the structural safety of mechanical structures, systems, and components (SSC) associated with nuclear power plants. These evaluation criteria, however, have inevitable limitations in accounting for the structural behaviors of spent nuclear fuel (SNF) transport casks, which likely undergo significant plastic deformations in extreme accidents. Hence, the stress-based evaluation criteria are considered inappropriate for energy-limited events that involve a high impact load, such as an accidental drop. This study evaluates the effectiveness of strain-based criteria, which were recently added in ASME Section III, Nonmandatory Appendix FF (American Society of Mechanical Engineers, 2015) and provides critical comparative study over traditional stress-based criteria for assessing the structural safety of SNF transport casks. Horizontal and vertical accidental drop events specified in NUREG-1536 (US Nuclear Regulatory Commission, 1997) are simulated using nonlinear dynamic finite-element analysis (FEA). Four SNF cask models with different impact-limiter designs are numerically simulated. The design of the impact limiter varies with wood types (redwood and balsa wood) and grain directions (transverse and longitudinal with respect to the loading direction). The FEA stress and strain results for the basket and canister parts are examined according to both stress-based and strain-based criteria. The strain-based criteria provide less conservative and more sensitive estimation than the stress-based criteria. Highlights Four spent nuclear-fuel cask models with different impact-limiter designs are numerically simulated. The baskets and canister were successfully protected from drop impact loads by the energy absorption of the impact limiters. The cask design satisfied both the stress-based and strain-based acceptance criteria. The stress-based design criteria are deemed quite more conservative than the strain-based design criteria.

주제어

참고문헌 (25)

American Society of Mechanical Engineers 2010 ASME BPVC Section III - Rules for Construction of Nuclear Facility Components - Division 1. In Subsection NB: Class 1 Components
American Society of Mechanical Engineers 2015 ASME BPVC Section III - Rules for Construction of Nuclear Facility Components - Appendices
US Nuclear Regulatory Commission 1977 RG 1.59. In Regulatory Guide 1.59, Revision 2, Design Basis Floods for Nuclear Power Plants
US Nuclear Regulatory Commission 1997 NUREG-1536 In Standard review plan for dry cask storage systems
Prog. Nucl. Energy Woo 100 255 2017 10.1016/j.pnucene.2017.06.018 Analyzing public preference and willingness to pay for spent nuclear fuel facilities in South Korea: A latent class approach

상세보기
European Academies Science Advisory Council. (2014). Management of Spent Nuclear Fuel and its Waste. Retrieved from European Union, Luxembourg.
U.S. Department of Energy. (2013). Strategy for the Management and Disposal of Used Nuclear Fuel and High-level Radioactive Waste. Retrieved from Washington DC.
Kogberg, M., Ingvarsson, I. (2006). Operational experience from SFR - Final repository for low- and intermediate level waste in Sweden. (No. INIS-BE-V-001).
Public Engagement Commission on Spent Nuclear Fuel Management. (2014). Potential Scenarios and Programs for Requiring Public Opinion about Spent Nuclear Fuel Management Policy (In Korean). Retrieved from Korea.
Nuclear and Industrial Safety Agency of the Japanese Government. (2006). Technical Requirements on Interim Spent Fuel Storage Facility Using Dry Metal Cask. NISA-314c-06-02, (in Japanese).
Nucl. Eng. Des. Frano 280 634 2014 10.1016/j.nucengdes.2014.09.034 Structural performance of an IP2 package in free drop test conditions: Numerical and experimental evaluations

상세보기
Ann. Nucl. Energy Kim 37 4 546 2010 10.1016/j.anucene.2009.12.023 Dynamic impact characteristics of KN-18 SNF transport cask - Part 1: an advanced numerical simulation and validation technique

상세보기
Ann. Nucl. Energy Kim 37 4 560 2010 10.1016/j.anucene.2009.12.024 Dynamic impact characteristics of KN-18 SNF transport cask - Part 2: sensitivity analysis of modeling and design parameters

상세보기
Ann. Nucl. Energy Wu 42 18 2012 10.1016/j.anucene.2011.12.016 Dynamic response analysis of a spent-fuel dry storage cask under vertical drop accident

상세보기
Nucl. Eng. Des. Aquaro 240 4 706 2010 10.1016/j.nucengdes.2009.12.018 Numerical and experimental analysis of the impact of a nuclear spent fuel cask

상세보기
Nucl. Eng. Des. Jak？i 239 2 201 2009 10.1016/j.nucengdes.2008.10.010 Finite element modelling of the one meter drop test on a steel bar for the CASTOR cask

상세보기
Ann. Nucl. Energy Huang 36 213 2009 10.1016/j.anucene.2008.11.014 A study on dynamic impact of vertical concrete cask tip-over using explicit finite element analysis procedures

상세보기
Ann. Nucl. Energy Champiri 110 126 2017 10.1016/j.anucene.2017.06.028 Added mass effect for tip-over analysis of dry cask composite structures at two different scales

상세보기
American Society of Mechanical Engineers. (2015). ASME BPVC Section III - Rules for Construction of Nuclear Facility Components - Division 3. In Containments for Transportation and Storage of Spent Nuclear Fuel and High Level Radiactive Material and Waste. New York, NY: ASME.
US Nuclear Regulatory Commission. (1987). Nureg-0800. In Standard review plan for the review of safety analysis reports for nuclear power plants. Washington, DC: US Nuclear Regulatory Commission.
US Nuclear Regulatory Commission. (1989). RG 7.8. Load Combination for the Structural Analysis of Shipping Casks. Washington, DC: US Nuclear Regulatory Commission.
Dassault Systemes, (2015). ABAQUS 6.14 Documentation, Simulia Co., Providence, RI, USA.
American Society of Mechanical Engineers. (2004). ASME B&VC, Section II. In Properties. New York, NY: ASME.
Blandford 2007 Tensile Stress-Strain Results for 304L and 316L Stainless Steel Plate at Temperature. Paper presented at the ASME, Pressure Vessels and Piping Conference
US Nuclear Regulatory Commission 2007 RG 1.76. In Regulatory Guide 1.76, Revision 1, Design-basis tornado and tornado missiles for nuclear power plants

LOADING...

내보내기 구분	파일저장 인쇄 메일전송
구성항목	기본정보 상세정보 관리번호, 논문명, 저널/프로시딩명, 저자 , 발행년, 권, 호, 시작페이지, 끝페이지, 발행기관 관리번호, 논문명, 대등논문명, 저자 , 저널/프로시딩명, 발행기관, 발행년, 발행언어, 권, 호, 시작페이지, 끝페이지, ISBN, ISSN, 주제분야, 키워드, 초록(한글), 초록(영문), 저자(소속기관)
저장형식	Text(ASCII format) Excel format RefWorks Direct Export RIS format (for Reference Manager, ProCite, EndNote), Scholar's Aids, Mendeley
메일정보	받는사람 (필수) @ 보내는사람 (선택) @ 제목 내용 KISTI 검색결과 이메일 서비스
안내	총 건의 자료가 검색되었습니다. 다운받으실 자료의 인덱스를 입력하세요. (1-10,000) 검색결과의 순서대로 최대 10,000건 까지 다운로드가 가능합니다. 데이타가 많을 경우 속도가 느려질 수 있습니다.(최대 2~3분 소요) 다운로드 파일은 UTF-8 형태로 저장됩니다. 파일의 내용이 제대로 보이지 않을실 때는 웹브라우저 상단의 보기 -> 인코딩 -> 자동선택 여부를 확인하십시오. ~ Text(ASCII format) Excel format

연합인증

Stress-based vs. Strain-based safety evaluations of spent nuclear fuel transport casks in energy-limited events

Abstract ▼ AI-Helper

주제어

참고문헌 (25)

이 논문을 인용한 문헌

연구과제 타임라인

관련 콘텐츠

원문 URL 링크

이 논문과 함께 이용한 콘텐츠

AI-Helper ※ AI-Helper는 오픈소스 모델을 사용합니다.

선택된 텍스트

연합인증

Stress-based vs. Strain-based safety evaluations of spent nuclear fuel transport casks in energy-limited events

Abstract ▼ AI-Helper

주제어

참고문헌 (25)

이 논문을 인용한 문헌

연구과제 타임라인

전체(0) 논문(0) 특허(0) 보고서(0)

전체(0) 논문(0) 특허(0) 보고서(0)

관련 콘텐츠

원문 URL 링크

이 논문과 함께 이용한 콘텐츠

AI-Helper ※ AI-Helper는 오픈소스 모델을 사용합니다.

선택된 텍스트