RELAP5/MOD3 model and transient analyses for the MARIA research reactor in Poland

• Autorzy: Szczurek J. , Czerski P. , Bykowski W.
• Języki publikacji: EN

Abstrakty

EN

The RELAP5/MOD3 input data model of the MARIA research reactor has been developed to provide the capability for the analysis of the reactor core under loss of flow and reactivity insertion transients. The model was qualified against the reactor data at steady state conditions and, additionally, against the existing reliable experimental data for a transient initiated by the reactor scram. The results obtained with the code agree well with the experimental data. The RELAP transient simulation was performed for loss of forced flow accidents including two scenarios with protected and unprotected (no scram) reactor core. Calculations allow estimating time margin for reactor scram initiation and reactivity feedbacks contribution to the results. The presented input data model should be treated as the first step for developing of the model including the whole primary cooling circuit of the reactor.

Słowa kluczowe

EN

research reactor; transient analysis; neutronic parameters; qualification

• Wydawca: Institute of Nuclear Chemistry and Technology
• Czasopismo: Nukleonika
• Rocznik: 2004
• Tom: Vol. 49, nr 4
• Strony: 149--157
• Opis fizyczny: Bibliogr. 7 poz., rys.

Twórcy

autor

Szczurek J.

• Institute of Atomic Energy, 05-400 Otwock-Świerk, Poland, Tel.: [phone], Fax: [phone]

autor

Czerski P.

• Institute of Atomic Energy, 05-400 Otwock-Świerk, Poland, Tel.: [phone], Fax: [phone]

autor

Bykowski W.

• Institute of Atomic Energy, 05-400 Otwock-Świerk, Poland, Tel.: [phone], Fax: [phone]

Bibliografia

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