Published 2010
| Version v1
Book
A study on thermo-mechanical behavior of a fuel rod in an SCWR core
Creators
- 1. Power and Industrial Systems Research and Development Center, Toshiba Corporation, 4-1, Ukishima-Cho, Kawasaki-Ku, Kawasaki 210-0862 (Japan)
- 2. Power and Industrial Systems Research and Development Center, Toshiba Corporation, 8, Shinsugita-Cho, Isogo-Ku, Yokohama 235-8523 (Japan)
Description
A study on thermo-mechanical behavior of fuel rods for a Super-Critical Water cooled Reactor (SCWR) was carried out with consideration of transient condition. For abnormal control rod withdrawal during rated power operation, it was shown by calculation that cladding effective stress was kept in elastic condition of the cladding material. It is concluded that the cladding keeps its mechanical integrity even in transient condition. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 978-89448-081-2
- Imprint Title
- Proceedings of the 2010 International Congress on Advances in Nuclear Power Plants - ICAPP '10
- Imprint Pagination
- 2284 p.
- Journal Page Range
- p. 128-129
Conference
- Title
- 2010 International Congress on Advances in Nuclear Power Plants
- Acronym
- ICAPP '10
- Dates
- 13-17 Jun 2010
- Place
- San Diego, CA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 42097775
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTROL ELEMENTS; FUEL RODS; MECHANICAL PROPERTIES; REACTOR KINETICS; ROD EJECTION ACCIDENTS; STRESSES; SUPERCRITICAL STATE; THERMODYNAMIC PROPERTIES; WATER COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; FUEL ELEMENTS; KINETICS; PHYSICAL PROPERTIES; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS
Optional Information
- Notes
- 2 refs.