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      KCI등재 SCIE SCOPUS

      Evaluation and verification of a structural safety analysis for a type B transport package for a radioactive waste drum

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      https://www.riss.kr/link?id=A76274865

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      다국어 초록 (Multilingual Abstract)

      We conducted and verified the structural safety analyses for a type B transport package for a radioactive waste drum. The type B package is used to transport one high-level radioactive waste drum from a waste facility to a temporary site in a nuclear ...

      We conducted and verified the structural safety analyses for a type B transport package for a radioactive waste drum. The type B package is used to transport one high-level radioactive waste drum from a waste facility to a temporary site in a nuclear power plant. It is important that the structural integrity of a type B transport package should be maintained under normal transport conditions such as the free drop test, the stacking test and the penetration test, and accident conditions of transport such as the 9 m height free drop test and the puncture test. Based on the ASME Boiler and Pres-sure Vessel Code, Section Ⅲ, Division 3 we evaluated the structural safety integrity of the type B package for a radio-active waste drum using finite element analysis. For the stacking test condition the maximum stress is a very low value when compared with the stress limits. The impact of the penetration bar on the overpack does not affect the containment part. For the free drop test condition and the puncture test condition the local stresses appear at the impact part and the containment part connected with the inner structure. The maximum stresses for all of the conditions are lower than the stress limits, so the structural integrity of the type B package for a radioactive waste drum was maintained. Also, the structural safety analyses were verified by using the data acquired from the 9 m drop and the puncture tests of the real model. The analytic accelerations of the 9 m drop test are similar to the test results. For the puncture test condition the analytic result is conservative when compared to the test. The analysis for the structural safety of the type B package reveals conservative results and it is proved that its structural integrity is maintained under normal and accident conditions of transport.

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      목차 (Table of Contents)

      • Abstract
      • 1. Introduction
      • 2. Type B package for a radioactive waste drum
      • 3. Finite element analysis
      • 4. Evaluation of the structural safety analysis
      • Abstract
      • 1. Introduction
      • 2. Type B package for a radioactive waste drum
      • 3. Finite element analysis
      • 4. Evaluation of the structural safety analysis
      • 5. Verification of the structural safety analysis
      • 6. Conclusion
      • References
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      참고문헌 (Reference)

      1 "numerical and experimental investigations on the impact behavior of selected structures" 287-293, 1994

      2 "Structural, Thermal Analyses for Transport Package of Radioactive Waste" 2006

      3 "Safety Test of a Type B Radioactive Waste Transport Package" 2 (2): 73-82, 2005

      4 "Regulations for the safe transport of radioactive" 2001

      5 "Packaging and Transportation of Radioactive Material, Title 10, Part 71" 1997

      6 "IAEA Safety Standard Series No. TS-R-1" 2000

      7 "ASME Boiler & Pressure Vessel Code Sec.III Div. 3" 2004

      8 "ASME Boiler & Pressure Vessel Code Sec" 2004

      9 "ABAQUS User's Manual for Revision 6.5" Hibbit, Karlson & Sorenson Inc. 2006

      1 "numerical and experimental investigations on the impact behavior of selected structures" 287-293, 1994

      2 "Structural, Thermal Analyses for Transport Package of Radioactive Waste" 2006

      3 "Safety Test of a Type B Radioactive Waste Transport Package" 2 (2): 73-82, 2005

      4 "Regulations for the safe transport of radioactive" 2001

      5 "Packaging and Transportation of Radioactive Material, Title 10, Part 71" 1997

      6 "IAEA Safety Standard Series No. TS-R-1" 2000

      7 "ASME Boiler & Pressure Vessel Code Sec.III Div. 3" 2004

      8 "ASME Boiler & Pressure Vessel Code Sec" 2004

      9 "ABAQUS User's Manual for Revision 6.5" Hibbit, Karlson & Sorenson Inc. 2006

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      학술지 이력

      학술지 이력
      연월일 이력구분 이력상세 등재구분
      2023 평가예정 해외DB학술지평가 신청대상 (해외등재 학술지 평가)
      2020-01-01 평가 등재학술지 유지 (해외등재 학술지 평가) KCI등재
      2012-11-05 학술지명변경 한글명 : 대한기계학회 영문 논문집 -> Journal of Mechanical Science and Technology KCI등재
      2010-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2008-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2006-01-19 학술지명변경 한글명 : KSME International Journal -> 대한기계학회 영문 논문집
      외국어명 : KSME International Journal -> Journal of Mechanical Science and Technology
      KCI등재
      2006-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2004-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2001-01-01 평가 등재학술지 선정 (등재후보2차) KCI등재
      1998-07-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
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      기준연도 WOS-KCI 통합IF(2년) KCIF(2년) KCIF(3년)
      2016 1.04 0.51 0.84
      KCIF(4년) KCIF(5년) 중심성지수(3년) 즉시성지수
      0.74 0.66 0.369 0.12
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