Status of PACTEL facility
Creators
- 1. Technical Research Centre of Finland, Espoo (Finland). Nuclear Engineering Lab.
Description
Since 1976, the Nuclear Engineering Laboratory of the Technical Research Centre of Finland and Lappeenranta University of Technology have cooperated in the field of nuclear reactor thermal-hydraulics. During these years, a series of experimental facilities (REWET-I, -II, -III, VEERA) simulating pressurized water reactors (PWRs) have been built. The newest facility, PACTEL (Parallel Channel Test Loop), is an experimental out-of-pile facility designed to simulate the major components and system behaviour of a commercial PWR during postulated small and medium size break loss-of-coolant accidents (LOCAs), natural circulation and operational transients. A PACTEL natural circulation experiment has been carried out as an OECD/NEA international standard problem ISP 33. (2 refs., 3 figs., 2 tabs.)
Files
Additional details
Publishing Information
- ISBN
- 951-763-788-8
- Imprint Title
- Second international seminar of horizontal steam generator modelling
- Imprint Pagination
- 208 p.
- Journal Page Range
- p. 89-93.
- Report number
- LTKK-TJ--30
Conference
- Title
- 2. international seminar on horizontal steam generator modelling.
- Dates
- 29-30 Sep 1992.
- Place
- Lappeenranta (Finland).
INIS
- Country of Publication
- Finland
- Country of Input or Organization
- Finland
- INIS RN
- 26053113
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ECCS; FLOW MODELS; HEAT TRANSFER; LIQUID FLOW; LOSS OF COOLANT; NATURAL CONVECTION; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR SAFETY EXPERIMENTS; SCALE MODELS; SIMULATION; STEAM GENERATORS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; BOILERS; CONVECTION; COOLING SYSTEMS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID FLOW; MATHEMATICAL MODELS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; STRUCTURAL MODELS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS