Published November 2003 | Version v1
Miscellaneous Open

Reload core safety verification

  • 1. VUJE Trnava Inc.- Engineering, Design and Research Organization, 918 64 Trnava (Slovakia)

Description

This paper presents a brief look at the process of reload core safety evaluation and verification in Slovak Republic. It gives an overview of experimental verification of selected nuclear parameters in the course of physics testing during reactor start-up. The comparison of IAEA recommendations and testing procedures at Slovak and European nuclear power plants of similar design is included. An introduction of two level criteria for evaluation of tests represents an effort to formulate the relation between safety evaluation and measured values (Authors)

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Part of:
Proceedings of the thirteenth Symposium of Atomic Energy Research

Additional details

Publishing Information

Publisher
Kiadja and KFKI Atomenergia Kutatointezet
Imprint Place
Budapest (Hungary)
ISBN
963-372-630-1
Imprint Title
Proceedings of the thirteenth Symposium of Atomic Energy Research
Imprint Pagination
[833 p.]
Journal Page Range
p. 235-243
Report number
INIS-SK--2003-033

Conference

Title
13. Atomic Energy Research Symposium on WWER Physics and Reactor Safety
Dates
22-26 Sep 2003
Place
Dresden (Germany)

INIS

Country of Publication
Hungary
Country of Input or Organization
Slovakia
INIS RN
35034276
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
EXPERIMENTAL DATA; REACTOR CORES; REACTOR FUELING; REACTOR SAFETY; REACTOR START-UP; SAFETY ANALYSIS; VERIFICATION
Descriptors DEC
DATA; INFORMATION; NUMERICAL DATA; REACTOR COMPONENTS; SAFETY; START-UP

Optional Information

Notes
15 refs., 1 tab. Imprint:Next corporations organizations: VTT Energy, Technical Research Centre of Finland, P.O.Box 1604, FIN-02044 VTT (Finland); Fortum Nuclear Services Ltd., Rajatorpantie 8, Vantaa, POB 10-FIN-00048 FORTUM (FI); NPP Kozloduy, NPP 3321, Kozloduy (BG); Studsvik Scandpower AS (Norway); KFKI Atomic Energy Research Institute, Reactor Analysis Laboratory, H-1525 Budapest 114, POB 49 (Hungary); FZR - Forschungszentrum Rossendorf, Institute of Safety Research,P.O.Box 510119, D-01314 Dresden (Germany); Physics Faculty of Sofia University, Sofia (Bulgaria); NPP Kozloduy (Bulgaria); Framatome ANP GmbH, Erlangen (Germany); State Scientific and Technical Centre on Nuclear and Radiation Safety - 'SSTC N+RS', Radgospna st. 35-37, 03142 Kyiv (Ukraine); 'TUEV ENERGY CONSULT/TUEV' Sueddeutschland Bau und Betrib GmbH, Westendstrasse 199, 80868 Muenchen (Germany); Experimental +Design organization 'Gidropress', Podolsk (Russian Federation); Lappeenranta University of Technology, LUT, P.O.Box 20, FIN-53851 Lappeenranta (Finland); GRS - Gesellschaft fuer Anlagen - und Reactorsicherheit mbH (Germany); SE, a.s. - AE Bohunice, 919 31 Jaslovske Bohunice (Slovakia)