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학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2018.1
- 수록면
- 297 - 305 (9page)
이용수
초록· 키워드
오류제보하기
Fuel assembly (FA) bow in pressurized water reactor (PWR) cores is considered to be a complex processwith a large number of influencing mechanisms and several unknowns. Uncertainty and sensitivityanalyses are a common way to assess the predictability of such complex phenomena. To perform suchanalyses, a structural model of a row of 15 FAs in the reactor core is implemented with the finite-elementcode ANSYS Mechanical APDL. The distribution of lateral hydraulic forces within the core row is estimatedbased on a two-dimensional Computational Fluid Dynamics model with porous media, assumingsymmetric or asymmetric core inlet and outlet flow profiles. The influence of the creep rate on the bowamplitude is tested based on different creep models for guide tubes and fuel rods. Different FA initialstates are considered: fresh FAs or FAs with higher burnup, which may be initially straight or exhibit aninitial bow from previous cycles. The simulation results over one reactor cycle demonstrate that changesin the creep rate and the hydraulic conditions may have a considerable impact on the bow amplitudesand the bow patterns. A good knowledge of the specific creep behavior and the hydraulic conditions istherefore crucial for making reliable predictions.
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참고문헌 (12)
참고문헌 신청
G. Gentet / 2012 / Areva product experience in support of EPR fuel design / TopFuel 2012 Transactions
A. Wanninger / 2016 / Development of computational methods to describe the mechanical behavior of PWR fuel assemblies / Proceedings of the 47th Annual Meeting on Nuclear Technology (AMNT 2016)
A. Wanninger / 2016 / Screening sensitivity analysis of a PWR fuel assembly FEM structural model / TopFuel 2016 Conference Proceedings
RSK / 2015 / Verformungen von Brennelementen in deutschen Druckwasserreaktoren (DWR), RSK-Stellungnahme (474. Sitzung der Reaktor-Sicherheitskommission (RSK) am 18.03.2015)
P. Yvon / 1998 / Irradiation creep and growth of guide Thimble alloys / Proceedings of the International Symposium Fontevraud IV
A. Wanninger / 2016 / Development of computational methods to describe the mechanical behavior of PWR fuel assemblies / Proceedings of the 47th Annual Meeting on Nuclear Technology (AMNT 2016)
A. Wanninger / 2016 / Screening sensitivity analysis of a PWR fuel assembly FEM structural model / TopFuel 2016 Conference Proceedings
RSK / 2015 / Verformungen von Brennelementen in deutschen Druckwasserreaktoren (DWR), RSK-Stellungnahme (474. Sitzung der Reaktor-Sicherheitskommission (RSK) am 18.03.2015)
P. Yvon / 1998 / Irradiation creep and growth of guide Thimble alloys / Proceedings of the International Symposium Fontevraud IV
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