[en] This paper presents the experimental coolant loop facility mathematical model evaluation with computer program RELAP 5/mod1. Steady state calculation at 0 % heat power was made. (author)

[en] This paper presents NPP Krsko containment pressure and temperature increase during Loss of Coolant Accident (LOCA) and Main Steam Line Break (MSLB). Containment environmental condition calculation was performed by CONTEMPT4/MOD4 computer code. Design accident calculations were performed by RELAP4/MOD6 and RELAP5/MOD1 computer codes. Calculational abilities and application methodology of these codes are presented. The CONTEMPT code is described in more detail. The containment pressure and temperature time distribution are presented as well. (author)

[en] In this paper experimental coolant loop is presented. Model is capable to simulate the operation of primary coolant loop of nuclear power plant. Thermohydraulic transients are initiated by power excursions or coolant flow changes. (author)

[en] In 1986 the US NRC published a proposed rule making to tighten the requirements on nuclear plants with regard to their ability to deal safely with a total loss of all a-c electric power, both from external and internal sources of supply. The proposed rule would require all licensees and applicants to: 1. Assess the capability of their plants to cope with a total loss all a-c power(that is, determine the amount of time the plant could maintain core cooling and containment integrity with a-c power unavailable); 2. Have procedures and training to cope with such an event; 3. Make modification, if necessary, to cope with an acceptable minimum duration loss of all a-c power. A total loss of all a-c electric power has been identified as an 'unresolved safety issue' and subjected to considerably study. The article presents an idea to resolve this issue. (author)

[en] In this paper the method to calculate the nonsymetric transients in the nuclear power plant is presented. ALMOD 3W2 computer code with steam generator model GEVAP is applied to analyze partial loss of forced reactor coolant flow for NPP Krsko. (author)