Published 2006
| Version v1
Miscellaneous
Hot Cell Examination of Irradiation Hardening in Spacer Grid
- 1. Korea Nuclear Fuel Co. Ltd., Taejon (Korea, Republic of)
Description
Although zirconium alloys have been used in the nuclear material, better mechanical properties of the Zirconium alloy are required enough to keep the integrity in high burn-up. There have been many investigations into the zirconium alloy of cladding tube in the point of corrosion resistance and PCI (Pellet Cladding Interaction). However, the other researches about the spacer grid are relatively insufficient even though the regions are damaged in high burn up. In this study, spacer grid samples detached from fuel assembly during intermediate burnup (21GWd/tU, 44GWd/tU) were analyzed to observe the mechanical property change and fracture behavior of the spacer grid
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS autumn meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2006 autumn meeting of the KNS
- Dates
- 2-3 Nov 2006
- Place
- Kyongju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 38049312
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BURNUP; CLADDING; CORROSION RESISTANCE; FRACTURES; FUEL ASSEMBLIES; GRIDS; HARDENING; HOT CELLS; IRRADIATION; MECHANICAL PROPERTIES; SPACERS; ZIRCONIUM ALLOYS
- Descriptors DEC
- ALLOYS; DEPOSITION; ELECTRODES; EQUIPMENT; FAILURES; LABORATORY EQUIPMENT; SURFACE COATING; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 4 refs, 3 figs