The application of small specimen technique to evaluate tensile properties of irradiated materials
Description
It is very important to evaluate the radiation embrittlement characterizations of nuclear structural materials using small scale specimen to enhance the integrity of nuclear power plant. However, the reliability of the data from small specimen test should be obtained by adequate test method involving specimen and apparatus design ahead of its application. The specimen and apparatus design and analysis method which enhance reliability of small specimen test data according to the previous research results were listed in this report. The results of small specimen tension test for Korean- made reactor pressure vessel material conducted at room and high temperature, were listed and discussed in this report. As a result, the reliability of small specimen data was confirmed even though, the strengths and elongations of small specimens were little bit smaller than those of standard specimens. The resonable results were obtained from the tests conducted at room and high temperature for 3 kinds of un-irradiated and irradiated pressure vessel material and 1 heat of unirradiated and irradiated weld
Availability note (English)
Available from INIS in electronic form; Also available from Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)Files
36095342.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 58 p.
- Report number
- KAERI/TR--2640/2003
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 36095342
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- DESIGN; ELONGATION; EMBRITTLEMENT; NUCLEAR POWER PLANTS; PRESSURE VESSELS; RELIABILITY; TENSILE PROPERTIES; WELDED JOINTS
- Descriptors DEC
- CONTAINERS; DEFORMATION; JOINTS; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS
Optional Information
- Notes
- 6 refs, 20 figs, 4 tabs