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No abstract available

[en] Influence of induced by gamma radiation (up to 8 x 10 R) and by fast neutron flux (up to 10¹³ neutron/cm²) defects in KTP crystals on their laser strength at λ = 1.06 and 0.53 μm at the pulse duration of 10 ± 1 ns under single and repeated action of laser radiation is investigated. The laser strength of samples depends essentially on the level and character of their irradiation. For considered actions the laser strength decreases up to 5 times

[en] Data on behavior of plutonium fluoride and fission products (FP) dissolved in fuel composition are needed to calculate the duration of an operating cycle of the ADTT facility (Accelerator-Driver Transmutation Technologies) and to determine the effect of their equilibrium concentrations on nuclear-physical characteristics of reactor operation. The data on the FP fluoride solubility in the molten salts are of great important for some industrial processes (electrolytical metal deposition, development of physical-chemical mean for processes of chemical technology, etc.) As noted above, some information on this question is given in monography and articles. Data concerning fluoride salts are given in reports. However, it was impossible to make the substantial analysis of mutual solubility of fluoride melts. The primary investigation of CeF₃ and neodymium, samarium and lanthanum fluorides showed that the solubility of the melt LiF-BeF₂ and LiF-BeF₂-ThF₄ was a linear function of reverse temperature and increases from lanthanum to samarium in the row of rare-earth elements. Disagreement in estimation of plutonium trifluoride solubility and incomplete data on the solubility of rare-earth elements prompted this study

No abstract available

No abstract available

[en] The spectrophotometric method has been applied to determine the equilibrium concentrations of plutonium valent forms which appear as a result of Pu(3)+1/2 Cl₂ reversible Pu(4)+C^- reaction in melts of some alkali metal chlorides and their binary mixtures. The effect of some phenomena in chloride melts on the results of measuring the optical density is shown. The conventional equilibrium constant of the above reaction is determined. Its value is shown to depend on the salt-solvent cationic composition

[en] The experience gained in the field of the development of molten salt reactors (MSR) can be made a basis of chemical processing of the ABC/ATW liquid fuel. The following combination of two processing principles are proposed for the ABC/ATW fuel (LiF-BeF₂-PuF_3,(4) - MAF_n): - continious removal of radioactive gases, volatile impurities and 'noble fission products'; - portion-by-portion electrochemical processing with removal of rare earth elements and some other fission products at an autonomous plant. After processing the fuel salt is brought back to the blanket of the ABC/ATW complex. The analysis of information previously published in different countries allows for a safe assumption that the ABC/ATW fuel cycle with liquid fuel salt is feasible and can be demonstrated experimentally

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No abstract available