"TITLE","AUTHORS","SUBJECT","SUBJECT_RELATED","DESCRIPTION","PUBLISHER","AVAILABILITY","RESEARCH_ORG","SPONSORING_ORG","PUBLICATION_COUNTRY","PUBLICATION_DATE","CONTRIBUTING_ORGS","LANGUAGE","RESOURCE_TYPE","TYPE_QUALIFIER","JOURNAL_ISSUE","JOURNAL_VOLUME","RELATION","COVERAGE","FORMAT","IDENTIFIER","REPORT_NUMBER","DOE_CONTRACT_NUMBER","OTHER_IDENTIFIER","DOI","RIGHTS","ENTRY_DATE","OSTI_IDENTIFIER","PURL_URL" "Safety analysis of BWR-type reactors. Summarizing report; Sicherheitsanalyse fuer Siedewasserreaktoren. Zusammenfassende Darstellung","Kersting, E [ed.]; Linden, J von [ed.]; Mueller-Ecker, D [ed.]; Werner, W [ed.]","22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; SAFETY; RISK ASSESSMENT; PROBABILISTIC ESTIMATION; FEDERAL REPUBLIC OF GERMANY; REACTOR ACCIDENTS; SYSTEMS ANALYSIS; 220900; 210100; REACTOR SAFETY; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, BOILING WATER COOLED","","As reference plants the two units of the Grundremmingen NPP (KRB-B and KRB-C) were used, both of them BWR-KWU type reactors, series 72. In the course of the safety analysis, representative, safety-relevant events were studied which may lead to reactor core damages. The result of the analyses was that for accidents not controllable by operational and safety systems (danger states) an occurrence frequency of about 5.10{sup -5}/a is to be expected, that means the probability is of 1 to 20 000 per plant and year. This occurrence frequency does not take into account an additional afterheat removal and feed system under construction. Already in the course of the analyses, essential improvements of the plant technology and processes for controlling accidents were initiated. Part of them has been implemented in the plant and led to an increased plant safety. Due to the already implemented and envisaged system modifications, an overall high safety level will be achieved. The investigations performed supply concrete hints also for the assessment of other boiling water reactors. In addition, these analyses indentified problems which require further investigation and development. (orig./HP) [Deutsch] Als Referenzanlagen wurden die beiden Bloecke KKW Grundremming (KRB-B und KRB-C) herangezogen, beide SWR-KWU, Baulinie 72. In der Sicherheitsanalyse wurden repraesentative, sicherheitstechnisch relevante Ereignisse untersucht, die zu Schaeden am Reaktorkern fuehren koennen. Die Analysen ergeben, dass fuer die mit den Betriebs- und Sicherheitssystemen nicht beherrschten Ereignisablaeufe (Gefaehrungszustaende) eine Eintrittshaeufigkeit von ca. 5.10{sup -5}/a zu erwarten ist, d.h. die Wahrscheinlichkeit hierfuer liegt bei 1 zu 20 000 pro Anlage und Jahr. Nicht beruecksichtigt ist bei der angegebenen Eintrittshaeufigkeit im Bau befindliche zusaetzliche Nachwaermeabfuhr- und Einspeisesystem. Bereits waehrend der Analyse wurden wesentliche Verbesserungen der Anlagentechnik und der Prozeduren zur Stoerfallbeherrschung angeregt. Diese sind schon zum groessten Teil in der Anlage verwirklicht und haben zu einer Erhoehung der Anlagensicherheit gefuehrt. Durch die bereits realisierten und noch vorgesehenen Systemaenderungen wird ein insgesamt hohes Sicherheitsniveau erreicht. Fuer die Beurteilung anderer Siedewasserreaktoren liefern die Untersuchungen ebenfalls konkrete Hinweise. Durch die Analysen wurden auch Fragestellungen identifiziert, die weitere Untersuchungen und Entwicklungsarbeiten erforderlich machen. (orig./HP)","","OSTI; NTIS (US Sales Only); INIS","Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Koeln (Gemany)","Bundesministerium fuer Forschung und Technologie, Bonn (Germany)","Germany","1992-11-01","","German","Technical Report","","","","Other Information: PBD: Nov 1992","","Medium: X; Size: 119 p.","ON: DE95726933; CNN: Foerderkennzeichen BMFT RS 0794; ISBN 3-923875-45-2","GRS-95","","Other: ON: DE95726933; CNN: Foerderkennzeichen BMFT RS 0794; ISBN 3-923875-45-2; TRN: DE94FN609","https://doi.org/","","2008-02-12","10106186",""