Type of research: applied Duration from: 01/01/91. to 01/01/94. Papers on project (total): 92
Papers on project quoted in Current Contents: 2
Institution name: Fakultet elektrotehnike i računarstva, Zagreb (36) Department/Institute: Power System Department Address: Avenija Vukovar 39 City: 10000 - Zagreb, Croatia
Communication
Phone: 385 (0)1 61 29 907
Fax: 385 (0)1 61 29 890
E-mail: danilo.feretic@fer.hr
Summary: In the field of safety analyses of nuclear power
facilities (i.e. nuclear power plants) the research activities are oriented
to mathematical modeling of nuclear power plant systems and components.
Mathematical models (for deterministic and probabilistic analysis),
included in complex computer codes, are research subject of Electrical
Power Engineering Department in the Faculty of Electrical Engineering since
1982. The research is devided into following activities: * Detailed
study and the enhancement of the mathematical models and computer codes
for deterministic and probabilistic safety analyses * Validation and
verification of RELAP5/mod2 computer code using comparison of the
analyses for the experimental facility (ROSA - Japan, BETHSY - France, PMK
- Hungary) and NPP Krško * Development of the expert system for diagnosis
of nuclear power plant transients and accidents * Development of 3-D
nodal transient computer code on the base of two-group time dependent
diffusion equation with 6 groups of delayed neutrons and thermohydraulic
feedback. * Development of fast computer code for evaluation of PWR
nuclear power plant behavior * Analyses of the accidents that were not
presented in the Final Safety Analyses Report for NE Krško (Station
Blackout and Anticipated Transient Without Scram) * Containment
condition (pressure, temperature, radiation dose) calculation after design
basis accident (Loss of Coolant Accident and Steam Line Break) for the
purpose of electrical equipment qualification. * Calculation of form
loss factors for NPP Krško primary system components that will be used in
RELAP5/mod2 computer code * Probabilistic safety analysis for vital
systems of NPP Krško * Calculation of gaseous radioactive effluents
release and doses for specific transients
Keywords: safety analyses, nuclear power facilities, nuclear power plants, mathematical modeling, deterministic safety analysis, probabilistic safety analysis, validation and verification of computer codes, expert system, Station Blackout, Anticipated Transient Without Scram, containment condition calculation, design basis accident, electrical equipment qualification, form loss factors, radioactive effluents, dose calculation
Research goals: Further development, enhancement and detailed study
of the mathematical models and computer codes used in safety analyses of
nuclear power facilities. Development of the expert system for diagnosis
of nuclear power plant transients and accidents. Validation and
verification of the complex computer codes using the results of the
experimental facilities tests. Analysis of the containment ambient
conditions for the purpose of electrical equipment qualification.
Calculation of form loss factors for NPP Krško primary system components
and analysis of gaseous radioactive effluents release.
COOPERATION - INSTITUTIONS
Name of institution
: Gesellshaft fur Anlagen- und
Reaktorsicherheit (GRS) mbH Type of institution: University/Faculty Type of cooperation: Joint publishing of scientific papers City: 85748 - Garching, Njemačka
Name of institution
: Dipartimento di costruzioni meccaniche e
nucleari Universita di Pisa Type of institution: University/Faculty Type of cooperation: Joint project City: 56100 - Pisa, Italija
Name of institution
: International Atomic Energy Agency (IAEA) Type of institution: International organization Type of cooperation: Systematic exchange of information City: Beč, Austrija Other information about the project.