Reactor with a fast-resonance neutron spectrum, cooled by supercritical-pressure water with a bidirectional coolant flow scheme A. P. GlebovA. V. Klushin OriginalPaper Pages: 325 - 331
Method for calculating the characteristics of the damaging dose for VVÉR vessel steel V. A. PechenkinYu. V. KonobeevK. G. Rozanov OriginalPaper Pages: 332 - 339
Application of microplasma spark treatments for creating stable heat-resistant barriers on the surface of jackets of thermionic transducers in nuclear reactors N. M. Chigrinova OriginalPaper Pages: 340 - 345
Ultraphosphate glasses for immobilization of liquid plutonium-containing wastes G. B. BorisovA. V. NazarovL. P. Sukhanov OriginalPaper Pages: 346 - 349
89Sr production in a reactor with solution fuel Yu. I. VereshchaginD. V. MarkovskiiL. Tome OriginalPaper Pages: 350 - 358
Calculations of the corrections for the true summation of cascade γ rays on the basis of statistical simulation using evaluated nuclear data A. N. BerlizovV. N. DanilenkoA. S. Kazimirov OriginalPaper Pages: 359 - 364
Determination of γ-ray flux in a stopped VVR-SM reactor from the color-center formation in LiF M. A. MussaevaÉ. M. IbragimovaM. I. Muminov OriginalPaper Pages: 365 - 369
Measurement of the effective delayed-neutron dose by the α-Rossi method in water-containing media V. A. Dulin OriginalPaper Pages: 370 - 375
Computational estimate of tritium accumulation in heavy-water reactors É. B. StrakhovV. N. Vorob’evO. A. Smirnov Scientific and Technical Communications Pages: 376 - 377
Small linear ion accelerators based on polycylindrical cavities V. V. KobetsA. O. Sidorin OriginalPaper Pages: 378 - 380
Criterion for the optimal choice of delayed-neutron data B. D. Abramov OriginalPaper Pages: 385 - 388