The PMK-NVH experimental facility and the phenomena to be investigated
Creators
- 1. Hungarian Academy of Sciences, Budapest. Central Research Inst. for Physics
Description
The integral-type PMK-NVH test facility is a 1:2070 scaled model of the primary circuit of the WWER-type Paks Nuclear Power Plant. The operating pressure and temperature are 16 MPa and 623 K, respectively. The elevations are the same as in the plant. The scheduled time for the start-up is the end of 1984. The loop was designed for SB LOCA experiments above all, but operational transients can also be investigated. Paper presents the system description including instrumentation, control system and data acquisition. Some important phenomena to be expected from SB tests as they could be derived from pre-test calculations are also presented. The effect of the loop seals on the natural circulation, normal or reverse heat transfer in steam generators, core heat transfer at reduced primary circuit inventory are included. (orig.)
Additional details
Publishing Information
- Imprint Title
- 5th international meeting on thermal nuclear reactor safety. Proceedings. Vol. 3
- Imprint Pagination
- 736 p.
- Journal Page Range
- p. 1689-1701.
- Report number
- KFK--3880/3
Conference
- Title
- 5. international meeting on thermal nuclear reactor safety.
- Dates
- 9-13 Sep 1984.
- Place
- Karlsruhe (Germany, F.R.).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 16068519
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HUNGARY; LOSS OF COOLANT; MOCKUP; PWR TYPE REACTORS; REACTOR SAFETY EXPERIMENTS; RESEARCH PROGRAMS; WWER-4 REACTOR
- Descriptors DEC
- ACCIDENTS; DEVELOPING COUNTRIES; ENRICHED URANIUM REACTORS; EUROPE; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; STRUCTURAL MODELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS