Abstract: According to an embodiment, a nuclear fuel material recovery method of recovering a nuclear fuel material containing thorium metal by reprocessing an oxide of a nuclear fuel material containing thorium oxide in a spent fuel is provided. The method has: a first electrolytic reduction step of electrolytically reducing thorium oxide in a first molten salt of alkaline-earth metal halide; a first reduction product washing step of washing a reduction product; and a main electrolytic separation step of separating the reduction product. The first molten salt further contains alkali metal halide, and contains at least one out of a group consisting of calcium chloride, magnesium chloride, calcium fluoride and magnesium fluoride. The method may further has a second electrolytic reduction step of electrolytically reducing uranium oxide, plutonium oxide, and minor actinoid oxide in a second molten salt of alkali metal halide.

Abstract: According to an embodiment, a nuclear fuel material recovery method of recovering a nuclear fuel material containing thorium metal by reprocessing an oxide of a nuclear fuel material containing thorium oxide in a spent fuel is provided. The method has: a first electrolytic reduction step of electrolytically reducing thorium oxide in a first molten salt of alkaline-earth metal halide; a first reduction product washing step of washing a reduction product; and a main electrolytic separation step of separating the reduction product. The first molten salt further contains alkali metal halide, and contains at least one out of a group consisting of calcium chloride, magnesium chloride, calcium fluoride and magnesium fluoride. The method may further has a second electrolytic reduction step of electrolytically reducing uranium oxide, plutonium oxide, and minor actinoid oxide in a second molten salt of alkali metal halide.

Abstract: According to an embodiment, a nuclear fuel material recovery method of recovering a nuclear fuel material containing thorium metal by reprocessing an oxide of a nuclear fuel material containing thorium oxide in a spent fuel is provided. The method has: a first electrolytic reduction step of electrolytically reducing thorium oxide in a first molten salt of alkaline-earth metal halide; a first reduction product washing step of washing a reduction product; and a main electrolytic separation step of separating the reduction product. The first molten salt further contains alkali metal halide, and contains at least one out of a group consisting of calcium chloride, magnesium chloride, calcium fluoride and magnesium fluoride. The method may further has a second electrolytic reduction step of electrolytically reducing uranium oxide, plutonium oxide, and minor actinoid oxide in a second molten salt of alkali metal halide.

Abstract: According to an embodiment, a nuclear fuel material recovery method of recovering a nuclear fuel material containing thorium metal by reprocessing an oxide of a nuclear fuel material containing thorium oxide in a spent fuel is provided. The method has: a first electrolytic reduction step of electrolytically reducing thorium oxide in a first molten salt of alkaline-earth metal halide; a first reduction product washing step of washing a reduction product; and a main electrolytic separation step of separating the reduction product. The first molten salt further contains alkali metal halide, and contains at least one out of a group consisting of calcium chloride, magnesium chloride, calcium fluoride and magnesium fluoride. The method may further has a second electrolytic reduction step of electrolytically reducing uranium oxide, plutonium oxide, and minor actinoid oxide in a second molten salt of alkali metal halide.

Abstract: According to one embodiment, a method of separating and recovering metals whereby a mixture containing at least a first metal and a second metal, the second metal having a higher standard electrode potential than that of the first metal, is connected to an anode in a molten salt, and the first metal and the second metal are precipitated on a cathode in the molten salt by electrolysis, the method of separating and recovering metals comprising: a detection step of detecting a concentration change in each of a first metal ion and a second metal ion in the molten salt by a concentration change detection unit; a first electrolysis step of electrolyzing the first metal; a first recovery step of recovering a precipitated substance according to a detection in which a concentration decrease of the first metal ion, which is predefined in the concentration change detection unit, is detected in the detection step; a second electrolysis step of electrolyzing the second metal; and a second recovery step of recovering a pre

Abstract: A corium processing method includes a dissolution step of feeding the corium into a first molten salt and dissolving uranium oxide and plutonium oxide contained in an oxide solid from the corium; a nuclear fuel recovery step of recovering the uranium oxide and the plutonium oxide from the first molten salt; a metal recovery step of feeding the corium into a second molten salt and separating and recovering metal Fe and metal Zr by molten salt electrolysis; and a solidification step of solidifying and recovering residues of the corium.

Abstract: According to one embodiment, a method of separating and recovering metals whereby a mixture containing at least a first metal and a second metal, the second metal having a higher standard electrode potential than that of the first metal, is connected to an anode in a molten salt, and the first metal and the second metal are precipitated on a cathode in the molten salt by electrolysis, the method of separating and recovering metals comprising: a detection step of detecting a concentration change in each of a first metal ion and a second metal ion in the molten salt by a concentration change detection unit; a first electrolysis step of electrolyzing the first metal; a first recovery step of recovering a precipitated substance according to a detection in which a concentration decrease of the first metal ion, which is predefined in the concentration change detection unit, is detected in the detection step; a second electrolysis step of electrolyzing the second metal; and a second recovery step of recovering a pre

Abstract: The adder-subtractor includes a pre-processing circuit which divides three inputted terms into a mantissa having an exponent of maximum value, mantissa having an exponent of intermediate value and mantissa having an exponent of minimum magnitude and outputting a mantissa obtained by right-shifting the mantissa having the exponent of intermediate value and the mantissa having the minimum exponent of 2n+3 bits and adjusting digits and the mantissa having the maximum exponent, which reduces the mantissas from three to two terms, which carries out addition on the mantissas of the two terms, a normalization circuit which makes left shift so that the most significant bit becomes 1, a rounding circuit which uses an (n+3)th bit from the most significant bit as a new sticky bit, takes logical OR with the lower bits and performs rounding and an exponent operation unit which outputs a final exponent.

Abstract: The three-term input floating-point adder-subtractor includes a pre-processing circuit which divides three inputted terms into a mantissa having an exponent of maximum value, mantissa having an exponent of intermediate value and mantissa having an exponent of minimum magnitude and outputting a mantissa obtained by right-shifting the mantissa having the exponent of intermediate value and the mantissa having the minimum exponent with a width of 2n+3 bits and adjusting digits and the mantissa having the maximum exponent, a carry save adder (CSA) which reduces the mantissas from the pre-processing circuit from three terms to two terms, a carry look-ahead adder (CLA) which carries out addition on the mantissas of the two terms, a normalization circuit which makes a left shift so that the most significant bit becomes 1, a rounding circuit which uses an (n+3)th bit from the most significant bit as a new sticky bit, takes logical OR with the lower bits and performs rounding and an exponent operation unit which output

Abstract: In a thermal recording sheet including a substrate having thereon a thermal color developing layer containing colorless or pale colored basic achromatic dye and an organic color developer, the thermal color developing layer contains aluminium hydroxide and a urea-formaldehyde resin pigment. The thermal recording sheet is small in abrasion of the recording head and adherence of depositions to the head even after long-run recording, and friction staining in unrecorded portion due to the recording head and change in gloss in unrecorded portion during recording are small.