VPBER-600 CONCEPTUAL FEATURES AND SAFETY ANALYSIS RESULTS

Citation
Fm. Mitenkov et al., VPBER-600 CONCEPTUAL FEATURES AND SAFETY ANALYSIS RESULTS, Nuclear safety, 34(2), 1993, pp. 237-241
Citations number
NO
Categorie Soggetti
Environmental Sciences","Nuclear Sciences & Tecnology
Journal title
ISSN journal
00295604
Volume
34
Issue
2
Year of publication
1993
Pages
237 - 241
Database
ISI
SICI code
0029-5604(1993)34:2<237:VCFASA>2.0.ZU;2-L
Abstract
This article describes a Russian approach to designing an enhanced-saf ety pressurized-water reactor. The basic design philosophy rests on th e concept of self-actuating passive systems without the need for activ e human intervention. An emergency decay heat-removal system independe nt of normal operating systems and functioning passively is described as well as provisions for ensuring the safely of the system in the eve nt of any accidents resulting in a loss of integrity of the cooling sy stem. The system is designed to have negative reactivity coefficients in all operating regimes and provides passive protection against malfu nction by any systems capable of adding reactivity to the reactor. The design uses a guard vessel enclosing the reactor and the primary cool ant loop.