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Afanas'ev, V.A.; Gryazev, V.M.; Efimov, V.N.; Krasnoyarov, N.V.; Skulkin, N.N.
Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (USSR)1978
Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (USSR)1978
AbstractAbstract
[en] The components of the temperature and power reactivity coefficients of the BOR-60 reactor have been experimentally and theoretically investigated. The dependence of the coefficients on the reator power, fuel burnup, coolant flow rate and inlet temperature have been measured. In measuring the coefficients by a dynamic method the time constants of some reactor constituents have been determined. A satisfactory agreement has been observed between theory and practice. The temperature coefficient has proved weakly dependent on the reactor parameters and time. The power coefficient has a complicated dependence on the parameters and decreases with time. The developed technique of calculating the reactivity balance alongside the analysis of the reactivity components provides for early diagnostics of the reactor
Original Title
Analiz ehffectov reaktivnosti kak sredstvo diagnostiki sostoyaniya bystrogo reaktora
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Source
1978; 24 p; 9 refs.; 5 figs.; 3 tables.
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Report
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