Spent Fuel Behaviors under Loss of Cooling/Coolant Accident in A Spent Fuel Pool
- 1. KAERI, Daejeon (Korea, Republic of)
Description
Under dry storage conditions for spent nuclear fuels, creep deformation/rupture is the most probable degradation mechanism for the cladding material, because internal pressure of the fuel rod also becomes higher with storage temperature. Thus the integrity of spent fuel during dry storage has been evaluated by predicting creep deformation of Zr alloy claddings. In particular, the hoop-directional creep behavior of high burn-up fuel cladding is concern due to the difference of pressure between fuel-cladding gap and storage environment. Many investigations have been performed in order to validate the hydrogen effect on creep behavior of fuel cladding, because high burn-up fuel cladding contains high concentration of hydrogen absorbed during waterside corrosion during normal operation. But there is no consensus regarding hydrogen effect on creep behavior. Accordingly, it is essential to clarify hydrogen effect on creep behavior of the high burn-up fuel cladding. It was revealed that hydrogen in the Zr alloy plays a role to increase secondary creep rate. The creep rate of irradiated(high burn-up) cladding is highest, and hydrided cladding > un-hydrided cladding.
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2016 spring meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2016 spring meeting of the KNS
- Dates
- 11-13 May 2016
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 48048739
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AFTER-HEAT REMOVAL; CLADDING; CREEP; DRY STORAGE; FEASIBILITY STUDIES; FUEL RODS; LOSS OF COOLANT; SPENT FUELS; STORAGE; ZIRCALOY 4
- Descriptors DEC
- ACCIDENTS; ALLOYS; ALLOY-ZR98SN-4; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; DEPOSITION; ENERGY SOURCES; FUEL ELEMENTS; FUELS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; IRON ADDITIONS; IRON ALLOYS; MATERIALS; MECHANICAL PROPERTIES; NUCLEAR FUELS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR MATERIALS; REMOVAL; STORAGE; SURFACE COATING; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- 5 refs, 2 figs