Published June 16, 1997 | Version v1
Miscellaneous

Comparison of ESCADRE mod 1.0. and modified version Source Term Code Package Code Systems on the Analysis of S1B Sequence for WWER-440 (V-213) Reactor Unit

Creators

  • 1. Nuclear Power Plants Research Institute Trnava a.s., Okruzna 5, 918 64 Trnava (Slovakia)

Description

This paper presents an application of the code system ESCADRE mod 1.0, devoted for severe accident analysis of PWR up to source term evaluation, to a WWER-440 (V-213) NPP. The basic results of S1B severe accident sequence (100 mm cold leg LOss of Coolant Accident connected with station blackout) are described and selected physical parameters are compared with the results obtained with modified version Source Term Code Package. The comparison is deliberated mainly on the timing of main primary circuit events and fission product release from fuel, aerosols transport in the primary circuit, confinement thermal-hydraulic behaviour, aerosols retention in the confinement and fission products leakage to the environment through permanent uptightness

Availability note (English)

Available from Nuclear Power Plants Research Institute Trnava a.s., Okruzna 5, 918 64 Trnava (Slovak Republic).

Additional details

Publishing Information

Imprint Pagination
13 p.

Conference

Title
International Conference on Severe Accident Risk and Management.
Dates
16-18 Jun 1997.
Place
Piestany (Slovakia).

Optional Information