Can heat be taken from the environment for free? von Kazachkovskii, O. D.

Volltext

Thermal shock in the cans of fuel rods von Kazachkovskii, O.D.

Volltext

Temperature flattening in fuel-element assemblies by using the method of eigenfunctions von Kazachkovskii, O. D.

Volltext

Determination of the breeding characteristics of nuclear fuel in fast reactors von Kazachkovskii, O. D., Matveev, V. I., Troyanov, M. F.

Volltext

Accelerating heat and mass transfer in fast-reactor fuel-pin assemblies with oppositely wound wire windings von Zhukov, A. V., Kazachkovskii, O. D., Matyukhin, N. M., Rymkevich, K. S., Sorokin, A. P.

Volltext

Study of the possibility of using thorium in fast power reactors von Leipunskii, A.I., Kazachkovskii, O.D., Shikhov, S.B., Murogov, V.M.

Volltext

An investigation of transient states of natural circulation in multi-circuit nuclear reactor systems von Bagdasarov, Yu.E., Kazachkovskii, O.D., Pinkhasik, M.S., Pyshin, V.K.

Volltext

The effect of nucleon number parity on the magnitude of radiative capture cross sections von Belanova, T.S., Kazachkovskii, O.D.

Volltext

The use of non-uranium plutonium diluents in large fast breeder reactors von Leipunskii, A.I., Kazachkovskii, O.D., Shikhov, S.B., Yurova, L.N., Khromov, V.V., Shmelev, A.N., Sukhorukin, V.K.

Volltext