Water Loop System Development for IASCC tests at High Temperature
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
The effect of a irradiation on a stress corrosion cracking (SCC) at a high temperature is needed for an application of new materials to a pressurized water reactor. Proton irradiation technique as an alternative tool of a neutron irradiation seems to appeal to evaluate the effect on the SCC behavior of stainless steels. The SCC technique can be used for a screening of various material and environmental conditions. However, the proton-irradiation should be confirmed for its role of in-core irradiation on crack growth and in performing a final verification of the effect of alternative irradiation on candidate alloys. In spite of the handicap of the proton irradiation, some test plans have been set up by using the proton irradiated materials due to a good feature of the technique such as a low radioactivity. This paper aims to introduce the SCC test facility for IASCC on the proton-irradiated materials
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS autumn meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2008 autumn meeting of the KNS
- Dates
- 30-31 Oct 2008
- Place
- Pyongchang (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 40066650
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CRACK PROPAGATION; CRACKING; PWR TYPE REACTORS; STAINLESS STEELS; STRESS CORROSION; TEMPERATURE RANGE 0400-1000 K; VERIFICATION
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; CORROSION; DECOMPOSITION; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; POWER REACTORS; PYROLYSIS; REACTORS; STEELS; TEMPERATURE RANGE; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 1 ref, 2 figs