Published 1990
| Version v1
Report
Status of work on the Maria test installation and algorithms of the first three experiments in the programme
Creators
- 1. Institute of Nuclear Research, Warsaw (Poland)
- 2. Gidropress, Experimental Design Bureau (USSR)
- 3. Kurchatov Nuclear Energy Inst., Moscow (USSR)
Description
The first part of the paper gives a brief description of the status of work on the MARIA test installation. Since the end of 1985 Finland has also been participating in the construction work together with Poland and the USSR. In the first half of 1986 the programme and the algorithms for carrying out the first three experiments were brought into line with the parameters of the WWER-440 reactor. Similar experiments were also to be carried out with the parameters of the WWER-1000 reactor. The second part of the paper describes these three experiments (large leak - basic case, large leak with delayed response of the reactor emergency cooling system and small leak with ejection of coolant over the pressure vessel). (author)
Availability note (English)
Available from Windscale Laboratory, Seascale, Cumbria, CA20 1PF.Additional details
Publishing Information
- Imprint Pagination
- 18 p.
- Report number
- Windscale-Trans--1190
Conference
- Title
- CMEA seminar 'thermo-physics TF 86'.
- Dates
- 7-9 Oct 1986.
- Place
- Rostock (German Democratic Republic).
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 22019529
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature, Translation
- Descriptors DEI
- ALGORITHMS; ECCS; FLOW RATE; FLUID FLOW; FUEL CANS; LOSS OF COOLANT; MARIA REACTOR; PERFORMANCE; PRIMARY COOLANT CIRCUITS; RESEARCH PROGRAMS; TEST FACILITIES; WWER-3 REACTOR
- Descriptors DEC
- ACCIDENTS; BERYLLIUM MODERATED REACTORS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; METAL MODERATED REACTORS; POOL TYPE REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- Translated from German, Kernenergie 30(8) (1987) p. 313-320.