Published 1993 | Version v1
Report Restricted

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

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Part of:
Second international seminar of horizontal steam generator modelling

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).

Optional Information