Published November 2009 | Version v1
Report

SWR 1000. Annex 11

Creators

Description

In the past, different investigations concerning the emergency cooling were done. Besides the R and D work of FRAMATOME an experimental testing program was conducted at other German and European research centers to provide verification of the mode of operation and effectiveness of the SWR 1000's passive safety systems. During 1996-1998 the European Union supported the BWR R and D Cluster of innovative passive safety systems, where the FZ Juelich, Germany, the GRS Cologne, Germany, the NRG Petten, The Netherlands, NRG Arnheim, The Netherlands, PSI, Switzerland, SIET Piacenca, Italy, STORK NUCON, The Netherlands and VTT Espoo, Finland were involved. Two large test facilities (NOKO, FZ Juelich for separate effect tests and PANDA, PSI for integral tests) delivered experimental data. In addition operational data from the Doodewaard NPP were used. Posttest calculations were performed using system codes: ATHLET, RELAP and TRAC; lumped parameter codes such as COCOSYS, RALOC and GOTHIC. The CFD-codes applied were CFX and PHOENIX. During the single effect tests, the heat transfer capability of the emergency condensers and the containment cooling condensers were investigated thoroughly. Special attention was directed to the simulation of condensation in horizontal tubes and to 3D stratification phenomena in the surrounding pools

Part of:
Passive safety systems and natural circulation in water cooled nuclear power plants

Additional details

Additional titles

Augmented title (English)
Passive safety systems and natural circulation in water cooled nuclear power plants

Publishing Information

ISBN
978-92-0-111309-2
Imprint Title
Passive safety systems and natural circulation in water cooled nuclear power plants
Imprint Pagination
159 p.
Journal Page Range
p. 89-94
ISSN
1011-4289
Report number
IAEA-TECDOC--1624

Optional Information

Notes
5 figs