Evaluation of the Neutron Irradiation Embrittlement of RPV Steels: Development of Embrittlement Trend Curve and Investigation of Through Wall Attenuation
- 1. Central Research Institute of Electric Power Industry (Japan)
Description
Full text: Accurate estimation of the through-wall mechanical property profile (attenuation) in reactor pressure vessel (RPV) steels is the key technology to evaluate the structural integrity of the RPVs of light water reactors. Prediction of the amount of embrittlement of RPV steels due to neutron irradiation during plant operation is the most important part of the estimation, and huge amount of efforts have been devoted worldwide to develop accurate and reliable embrittlement trend curves (ETCs). On the other hand, consideration of the profile of initial mechanical property through the wall thickness of RPV steels is also very beneficial in evaluating the actual structural integrity of RPVs. In this talk, we will review the development of ETCs for the RPV steels in Japan, and demonstrate recent results on the research activity on through-wall attenuation. (author)
Additional details
Identifiers
Publishing Information
- Publisher
- IAEA
- Imprint Place
- Vienna (International Atomic Energy Agency (IAEA))
- ISBN
- 978-92-0-106921-4
- Imprint Title
- Nuclear Power Plant Life Management. Proceedings of an International Conference. Supplementary Files
- Imprint Pagination
- vp.
- Series
- Proceedings Series
- Journal Page Range
- 1 p.
- ISSN
- 0074-1884
Conference
- Title
- 4. International Conference on Nuclear Power Plant Life Management
- Dates
- 23-27 Oct 2017
- Place
- Lyon (France)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 52045409
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATTENUATION; EMBRITTLEMENT; EVALUATION; FORECASTING; IRRADIATION; JAPAN; MECHANICAL PROPERTIES; NEUTRONS; PRESSURE VESSELS; REACTOR OPERATION; STEELS; THICKNESS; WATER COOLED REACTORS; WATER MODERATED REACTORS
- Descriptors DEC
- ALLOYS; ASIA; BARYONS; CARBON ADDITIONS; CONTAINERS; DEVELOPED COUNTRIES; DIMENSIONS; ELEMENTARY PARTICLES; FERMIONS; HADRONS; IRON ALLOYS; IRON BASE ALLOYS; NUCLEONS; OPERATION; REACTOR LIFE CYCLE; REACTORS; TRANSITION ELEMENT ALLOYS
Optional Information
- Secondary number(s)
- STI/PUB--1940(SUPPLEMENTARY FILES); IAEA-CN--246