Published 1994
| Version v1
Book
NESC spinning cylinder project for the evaluation of RPV integrity
Creators
- 1. AEA Technology, Risley (United Kingdom). Structural Integrity Division
- 2. Health and Safety Executive, Merseyside (United Kingdom). Nuclear Safety Division
- 3. Inst. of Advanced Materials, Petten (Netherlands). CEC Joint Research Centre
Description
The Network for Evaluating Steel Components (NESC) was launched in 1993 to address the reliability of the entire structural integrity assessment process. NESC builds on the experience of PISC and FALSIRE. The first experiment NESC1 is jointly sponsored by the UK Health and Safety Executive, CEC with contributions in kind from participating organizations. This paper outlines the progress to date of the first experiment NESC1 which makes use of the large scale test facilities at Risley Nuclear Laboratories
Additional details
Additional titles
- Augmented title (English)
- Reactor Pressure Vessel
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-1361-4
- Imprint Title
- Service experience and reliability improvement: Nuclear, fossil, and petrochemical plants. PVP-Volume 288
- Imprint Pagination
- 437 p.
- Journal Page Range
- p. 85-93.
Conference
- Title
- 1994 pressure vessels and piping conference.
- Dates
- 19-23 Jun 1994.
- Place
- Minneapolis, MN (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26021921
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGE DEPENDENCE; CRACKS; FRACTURE PROPERTIES; INSPECTION; INTERNATIONAL ORGANIZATIONS; PRESSURE VESSELS; PWR TYPE REACTORS; RELIABILITY; RISK ASSESSMENT; SAFETY ANALYSIS; STEELS; THERMAL SHOCK
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CONTAINERS; ENRICHED URANIUM REACTORS; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-940613--.