지원사업
학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
커뮤니티
연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.3
- 수록면
- 988 - 1,003 (16page)
- DOI
- https://doi.org/10.1016/j.net.2020.08.011
이용수
초록· 키워드
오류제보하기
Existing elastic analysis methods cannot be adhered to in order to assess the structural integrity of areactor vessel and internals for a beyond design basis earthquake. Elasto-plastic analysis methods arerequired, and the factors that affect the elasto-plastic behavior of reactor materials should be taken intoaccount. In this study, a material behavior model was developed that considers the irradiation embrittlement effect, which affects the elasto-plastic behavior of the reactor material. This was used to performthe elasto-plastic time history analyses of the reactor vessel and its internals for beyond design basisearthquake. For this investigation, appropriate beyond design basis earthquakes and reliable finiteelement models were used. Based on the analysis results, consideration was given to the load reductioneffect and the margin change. These were transferred to the internals due to the plastic deformation ofthe reactor vessel.
목차
등록된 정보가 없습니다.
참고문헌 (33)
참고문헌 신청
IAEA / Non-linear Response to a Type of Seismic Input Motion
International Atomic Energy Agency IAEA / 2000 / Safety of Nuclear Power Plants:Design environmentSpecific Safety Requirements, No. SSR-2/1 (Rev.1)
P. R. Donavin / 2016 / Technical basis for proposed ASME section XI code case on beyond design bases earthquake / Am. Soc. Mech. Eng. Press. Vessel. Pip. Div. PVP
T. Watakabe / 2013 / Study on piping response under multiple excitation Part 1: triple shaking table test of piping having three-supporting points / Am. Soc. Mech. Eng. Press. Vessel. Pip. Div. PVP
S. Kai / 2013 / Study on piping response under multiple excitation Part 2: validation for multiple analysis of piping / Am. Soc. Mech. Eng. Press. Vessel. Pip. Div. PVP
International Atomic Energy Agency IAEA / 2000 / Safety of Nuclear Power Plants:Design environmentSpecific Safety Requirements, No. SSR-2/1 (Rev.1)
P. R. Donavin / 2016 / Technical basis for proposed ASME section XI code case on beyond design bases earthquake / Am. Soc. Mech. Eng. Press. Vessel. Pip. Div. PVP
T. Watakabe / 2013 / Study on piping response under multiple excitation Part 1: triple shaking table test of piping having three-supporting points / Am. Soc. Mech. Eng. Press. Vessel. Pip. Div. PVP
S. Kai / 2013 / Study on piping response under multiple excitation Part 2: validation for multiple analysis of piping / Am. Soc. Mech. Eng. Press. Vessel. Pip. Div. PVP
함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
Determination of earthquake safety of RC frame structures using an energy-based approach
Computers and Concrete, An International Journal
2017 .01
-
유한요소해석을 이용한 Beam 요소 기반 배관계 탄소성 해석 결과 차이
대한기계학회 춘추학술대회
2020 .07
-
Event/accident Simulation Model of the Reactor Pressure Vessel Internal Segmentation Activity
한국방사성폐기물학회 학술대회
2019 .01
-
원자로용기 결함 조건에 따른 원자로 내부구조물 이상진동에 대한 유한요소 해석
한국소음진동공학회논문집
2023 .12
-
Analyze packing structure of elasto-plastic particle fibers in term of aspect ratio, bending stiffness, and surface energy
대한기계학회 춘추학술대회
2022 .11
-
설계방식에 따른 초고압 반응용기의 구조적 특성에 관한 연구
한국정밀공학회 학술발표대회 논문집
2018 .05
-
Vessel failure sensitivities of an advanced reactor for SBLOCA
Nuclear Engineering and Technology
2020 .01
-
Iterative global-local approach to consider the local effects in dynamic analysis of beams
Coupled systems mechanics
2017 .01
-
안전등급 1등급 기기 배관계에 대한 설계초과지진 하중에서의 동적 탄소성 시간이력 지진 해석에 관한 변수 영향 고찰
대한기계학회 춘추학술대회
2018 .02
-
Plastic Analysis and Design of Steel Structures
한국강구조학회지
2015 .06
-
Conceptual Design for Kori Unit 1 Reactor Vessel and Internal Segmentation Process
한국방사성폐기물학회 학술대회
2017 .01
-
Study on Segmentation Plan for Kori Unit 1 Reactor Vessel Internal
한국방사성폐기물학회 학술대회
2018 .01
-
EVALUATION OF HEAT-FLUX DISTRIBUTION AT THE INNER AND OUTER REACTOR VESSEL WALLS UNDER THE IN-VESSEL RETENTION THROUGH EXTERNAL REACTOR VESSEL COOLING CONDITION
Nuclear Engineering and Technology
2015 .01
-
한국의 2017-2019년 플라스틱 물질흐름분석
한국폐기물자원순환학회지
2022 .06
-
Study on Radiological Inventory Assessment of K 1 Reactor Vessel
한국방사성폐기물학회 학술대회
2019 .01
-
PGSFR 소듐냉각고속로 원자로용기 설계 및 구조건전성 평가
한국압력기기공학회 논문집
2016 .06
-
Segmentation and Packaging Plan for the Reactor Pressure Vessel
한국방사성폐기물학회 학술대회
2017 .01
-
Discovery of new biocatalyst for plastic biodegradation and future directions
한국생물공학회 학술대회
2021 .10
-
조사취화 영향을 고려한 원자로내부구조물의 운전응력 평가
대한기계학회 춘추학술대회
2016 .12
-
The Evolution of Bio-based Plastics beyond Petrochemical Plastics
한국고분자학회 학술대회 연구논문 초록집
2019 .10
이 논문의 저자 정보
최근 본 자료
댓글(0)
0