Published August 1999 | Version v1
Report

Safety analysis of uncontrolled closing of the steam line fast-acting valve - situation before and after reconstruction of the instrumentation and control system. Rev. 1

Description

The effect of upgrading of the instrumentation and control system was assessed based on a comparison of the 2 analyses. The conservatism of the analysis consisted in the most adverse core cooling condition, expressed in terms of the departure from nucleate boiling ratio (DNBR). The RELAP5/MOD3.1 code was used. The DNBR margin was evaluated by means of the standardized PI-1 correlation. The minimum DNBR reached was 1.63 and 1.42 for the situation before and after the I and C system reconstruction, which is well above the PI-1 correlation limit of 1.29. (P.A.)

Availability note (English)

Availability information: Deposited with Nuclear Research Institute Rez (NRI), 250 68 Rez, Czech Republic. For availability conditions contact the NRI Library, e-mail: ret@nri.cz

Additional details

Additional titles

Original title (Czech)
Bezpecnostni analyzy nerizeneho uzavreni RCA na parovodu pred a po obnove SKR. Revize 1
Augmented title (English)
[Dukovany NPP]

Publishing Information

Imprint Pagination
[59 p.]
Report number
UJV--11261-T

Optional Information

Notes
4 tabs., 60 figs., 18 refs.