Statistical data on reactor scrams - Data for 1993. Compiled by the NEA Secretariat from contributions by principal Working Group No. 1 of the OECD/NEA Committee on the Safety of Nuclear Installations
Description
At the OECD/NEA Symposium on Reducing Reactor Scram Frequency (Tokyo, April 1986), it was recommended that the collection of statistical data on reactor scrams be continued and updated regularly; this recommendation was subsequently endorsed by the NEA Committee on the Safety of Nuclear Installations (CSNI). As a follow-up to this initiative, the NEA Secretariat compiled a second issue of the statistical data on reactor scrams for 1987; that compilation was published as CSNI Report No. 157 in May, 1989. Based on the CSNI's recommendations, the NEA Secretariat subsequently produced annual reports entitled 'Statistical Data on Reactor Scrams', the most recent one being that for the 1993 scram data, issued in August 1994. The current report consists of graphs of the average scrams per unit, as well as the average scrams per 1000 hours critical with the turbine on-line, for the data collected during 1993, as well as graphs showing trends from 1989 to 1993. Part 1 gives one graph per country showing the trend for 1993 as well as graphs of percentage of main signals by plant designs; Part 2 is a compilation of tables and reports provided by Member countries
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Additional details
Publishing Information
- Imprint Pagination
- 142 p.
- Report number
- NEA-CSNI-R--1995-7
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 49053756
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- BWR TYPE REACTORS; DATA COMPILATION; GCR TYPE REACTORS; HUMAN FACTORS; PHWR TYPE REACTORS; PWR TYPE REACTORS; SCRAM; STATISTICAL DATA; SYSTEM FAILURE ANALYSIS
- Descriptors DEC
- DATA; DATA PROCESSING; ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; INFORMATION; NUMERICAL DATA; POWER REACTORS; PROCESSING; REACTOR LIFE CYCLE; REACTOR SHUTDOWN; REACTORS; SHUTDOWN; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS