Published November 1987
| Version v1
Journal article
Creep deformation of zircaloy fuel cladding under dry storage condition
Creators
- 1. Central Research Inst. of Electric Power Industry, Komae, Tokyo (Japan). Komae Research Lab.
Description
In this report, creep deformation behavior of zircaloy-4 nuclear fuel cladding was investigated under dry storage condition with relatively low stress level (internal pressure range from 35 to 70 atm. at room temperature). Testing time was up to 7400 hours. The results obtained were as follows; (1) There was no effect of oxidizing atomospher on the creep deformation characteristic of zircaloy-4 at temperature range 304 to 402 degree centigrade. (2) Strain hardening rule was applicable to creep deformation under stress and temperature fluctuating condition. (J.P.N.)
Additional details
Publishing Information
- Journal Title
- Denryoku Chuo Kenkyusho Hokoku
- Journal Issue
- no.T87011
- Series
- Denryoku Chuo Kenkyusho Hokoku.
- CODEN
- DCKHD
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 19083967
- Subject category
- S42: ENGINEERING; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- ALLOY-ZR98SN-4; CASKS; CREEP; DEFORMATION; DRY STORAGE; EXPERIMENTAL DATA; FUEL CANS; PRESSURE DEPENDENCE; SPENT FUEL STORAGE; SPENT FUELS; STRAINS; STRESSES; TEMPERATURE DEPENDENCE
- Descriptors DEC
- ALLOYS; CHROMIUM ADDITIONS; CONTAINERS; CORROSION RESISTANT ALLOYS; DATA; ENERGY SOURCES; FUELS; HEAT RESISTING ALLOYS; INFORMATION; IRON ADDITIONS; MATERIALS; MECHANICAL PROPERTIES; NUCLEAR FUELS; NUMERICAL DATA; REACTOR MATERIALS; STORAGE; TIN ALLOYS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS