Published 1989
| Version v1
Book
Developments in fracture mechanics and non-destructive examination
Creators
- 1. Commission of the European Communities, Ispra (Italy)
- 2. Nichols Consultants, Culcheth, Warrington (UK)
- 3. Stuttgart Univ. (Germany, F.R.)
- 4. Tokyo Univ. (Japan)
Description
The purpose of this chapter is to give a brief review of the major developments and trends that have occurred in some of the technical areas covered by Division G of SMiRT since the first conference was held in Berlin in 1971. As with any human activity, time and experience produce organic change so that the technical areas covered by Division G have changed somewhat over the 18 years of its existence. As first conceived by Tom Jaeger, Division G was one of two divisions devoted to Light Water Reactor Components other than fuel and cladding. Division F was conceived with Core Structures and Piping while Division G was devoted to the Steel Reactor Pressure Vessels
Additional details
Publishing Information
- Publisher
- American Association for Structural Mechanics in Reactor Technology.
- Imprint Place
- Los Angeles, CA (USA)
- ISBN
- 0-9623306-0-4
- Imprint Title
- Transactions of the 10th international conference on structural mechanics in reactor technology
- Imprint Pagination
- 404 p.
- Series
- Volume A. Principal division lectures.
- Journal Page Range
- p. 219-260.
Conference
- Title
- 10. international conference on Structural Mechanics in Reactor Technology (SMIRT).
- Dates
- 14-18 Aug 1989.
- Place
- Anaheim, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21068248
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FRACTURE MECHANICS; NONDESTRUCTIVE TESTING; NOZZLES; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR CORES; REACTOR SAFETY; STEELS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CONTAINERS; ENRICHED URANIUM REACTORS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS TESTING; MECHANICS; POWER REACTORS; REACTORS; SAFETY; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-890855--.