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
- 2020.1
- 수록면
- 802 - 810 (9page)
이용수
초록· 키워드
오류제보하기
Three-dimensional finite element simulations are implemented for the in-pile thermo-mechanical behavior in UeMo/Al monolithic fuel plates with different thermal creep rates of cladding involved. The numerical results indicate that the thickness increment of fuel foil rises with the thermal creep coefficient of cladding. The maximum Mises stress of cladding is reduced by ~85% from 344 MPa on the 98.0th day when the creep coefficient of cladding increases from 0.01 to 10.0, due to its equivalent thermal creep strain enlarged by 3.5 times. When the thermal creep coefficient of Aluminum cladding increases from 0 to 1.0, the maximum mesoscale stress of fuel foil varies slightly. At the same time, the peak mesoscale normal stress of fuel foil can reach 51 MPa on the 98.0th day for the thermal creep coefficient of 10, which increases by 60.3% of that with the thermal creep un-occurred in the cladding. The maximum through-thickness creep strain components of fuel foil differ slightly for different thermal creep coefficients of cladding. The dangerous region of fuel foil becomes much closer to the heavily irradiated sidewhen the creepcoefficientof cladding becomes 10.0.The creep performance of Aluminum cladding should be optimized for the integrity of monolithic fuel plates.
목차
등록된 정보가 없습니다.
참고문헌 (0)
참고문헌 신청함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
Thermal creep behavior of CZ cladding under biaxial stress state
Nuclear Engineering and Technology
2020 .12
-
Effect of Creep Deformation on Ductility of Simulated Spent Fuel Cladding
한국방사성폐기물학회 학술대회
2018 .01
-
Investigating creep behavior of Ni–Cr–W alloy pressurized tube at 950 °C by using in-situ creep testing system
Nuclear Engineering and Technology
2020 .01
-
Thermo-mechanical coupling behavior analysis for a U ? 10Mo/Al monolithic fuel assembly
Nuclear Engineering and Technology
2021 .09
-
Circumferential steady-state creep test and analysis of Zircaloy-4 fuel cladding
Nuclear Engineering and Technology
2021 .07
-
Thermal Aging Effects on Creep Rupture Behavior of Alloy 617
대한기계학회 춘추학술대회
2017 .11
-
Creep Rupture Characteristics of Cladding Tubes of FC92B and FC92N: Candidate Alloys of SFR Fuel Cladding Tube Materials
Metals and Materials International
2022 .06
-
Biaxial creep property of ethylene tetrafluoroethylene (ETFE) foil
Structural engineering and mechanics : An international journal
2015 .01
-
Biaxial creep property of ethylene tetrafluoroethylene (ETFE) foil
Structural Engineering and Mechanics, An Int＇l Journal
2015 .01
-
Preliminary study on the thermal-mechanical performance of the U3Si2 /Al dispersion fuel plate under normal conditions
Nuclear Engineering and Technology
2021 .11
-
대형 가스터빈 1단 베인 크리프 수명평가를 위한 탄성추종 계수 기반 크리프 응력 예측
대한기계학회 춘추학술대회
2017 .04
-
Laser cladding 표면의 젖음성 평가
한국트라이볼로지학회 학술대회
2019 .04
-
Modified projection model-based constant-stress creep curve for alloy 690 steam generator tube material
Nuclear Engineering and Technology
2022 .03
-
Creep 기반 화력발전 소재의 고온 수명 예측 기술 개발
한국기계가공학회 춘추계학술대회 논문집
2021 .12
-
실험을 통한 플라스틱 크리프 거동 특성 연구
한국정밀공학회 학술발표대회 논문집
2015 .05
-
An improved Maxwell creep model for salt rock
Geomechanics & engineering
2015 .01
-
레이저 클래딩 표면에 대한 젖음 특성에 관한 연구
한국기계가공학회지
2019 .11
-
Preliminary Study of Metal Cladding Process for Improving Impact Resistance
한국정밀공학회 학술발표대회 논문집
2017 .05
-
Creep strain modeling for alloy 690 SG tube material based on modifi ed theta projection method
Nuclear Engineering and Technology
2022 .05
-
금속 적층품 물성제어를 위한 하이브리드 DED Cladding 공정 연구
한국정밀공학회 학술발표대회 논문집
2022 .05
이 논문의 저자 정보
최근 본 자료
댓글(0)
0