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Journal Articles

IS process hydrogen production test for components and system made of industrial structural material, 2; H$$_{2}$$SO$$_{4}$$ decomposition, HI distillation, and HI decomposition section

Noguchi, Hiroki; Takegami, Hiroaki; Kamiji, Yu; Tanaka, Nobuyuki; Iwatsuki, Jin; Kasahara, Seiji; Kubo, Shinji

Proceedings of 8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016) (CD-ROM), p.1029 - 1038, 2016/11

JAEA has been conducting R&D on the IS process for nuclear-powered hydrogen production. We have constructed a 100 NL/h-H$$_2$$-scale test apparatus made of industrial materials. At first, we investigated performance of components in this apparatus. In this paper, the test results of H$$_2$$SO$$_4$$ decomposition, HI distillation, and HI decomposition were shown. In the H$$_2$$SO$$_4$$ section, O$$_2$$ production rate is proportional to H$$_2$$SO$$_4$$ feed rate and SO$$_3$$ decomposition ratio was estimated about 80%. In HI distillation section, we confirmed to acquire a concentrated HI solution over azeotropic HI composition in the condenser. In HI decomposition section, H$$_2$$ could be produced stably by HI decomposer and decomposition ratio was about 18%. The H$$_2$$SO$$_4$$ decomposer, the HI distillation column, and the HI decomposer were workable. Based on the results added to that shown in Series I, we conducted a trial continuous operation and succeeded it for 8 hours.

Journal Articles

Hydrogen isotope separation by cryogenic distillation

Yamanishi, Toshihiko

Purazuma, Kaku Yugo Gakkai-Shi, 92(1), p.21 - 25, 2016/01

AA2015-0316.pdf:0.93MB

In a fusion reactor, the hydrogen isotope separation system is required in the fuel cycle system to supply deuterium (D) and tritium (T) as its fuel. In ITER, 90% of T must be recycled through the isotope separation system. On the other hand; since the hydrogen (H) gas is finally exhausted to the environment, the T concentration in the H gas from the isotope separation system should be as low as reasonable achievable. Hence, the isotope separation system of a fusion reactor must have a large separation factor. The flow rate of the isotope separation system of a fusion reactor reaches to 300 mol/h. Only the cryogenic distillation method can meet the above conditions (large flow rate and separation factor) and is most likely used as a hydrogen separation system in a fusion reactor. In this chapter, several simulation methods and a set of experimental data of the cryogenic distillation columns are described in detail.

Journal Articles

Numerical analysis of fractional distillation characteristics for radioactive metallic waste vaporized in the shape of atomic beam

Akaoka, Katsuaki; Maruyama, Yoichiro

Nihon Genshiryoku Gakkai Wabun Rombunshi, 4(2), p.127 - 134, 2005/06

The fractional distillation characteristics of the materials used for the reactor pressure vessel made of ASTM A302B and the structures in reactor made of SUS304 which are the radioactive metallic waste of Japan Power Demonstration Reactor (JPDR) were analyzed numerically. In the simulation, the vaporization rates of the components of the waste were calculated by using the Langmuir's equation and Henry's law. As the result of simulation, it was calculated that $$^{152}$$Eu, $$^{154}$$Eu, $$^{14}$$C and $$^{94}$$Nb can be reduced to less than clearance level by the fractional distillation. On the ASTM A302B case, it was pointed out that the other radioactive nuclei which are $$^{54}$$Mn, $$^{55}$$Fe, $$^{60}$$Co, $$^{59}$$Ni and $$^{63}$$Ni satisfy clearance level after 77 years cooling down. On the SUS304 case, it was pointed out that $$^{59}$$Ni and $$^{63}$$Ni must be separated to satisfy clearance level using isotope separation.

Journal Articles

Distillation of cadmium from uranium-plutonium-cadmium alloy

Kato, Tetsuya*; Iizuka, Masatoshi*; Inoue, Tadashi*; Iwai, Takashi; Arai, Yasuo

Journal of Nuclear Materials, 340(2-3), p.259 - 265, 2005/04

 Times Cited Count:22 Percentile:82.13(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Numerical analysis of fractional distillation for radioactive metal

Akaoka, Katsuaki; Maruyama, Yoichiro

RIST News, (39), p.23 - 31, 2005/03

For the separation of radionuclide from the radioactive metallic waste generated by the decommissioning of nuclear facilities, a new method combined with the distillation and laser separation is being studied. The characteristics of fractional distillation for duralumin were analyzed numerically using the Henry's law and the Langmuir's equation, and its result agreed well with the experiment. Next, the fractional distillation characteristics of the materials used for the structures in reactor made of SUS304 which are the radioactive metallic waste of Japan Power Demonstration Reactor (JPDR) were analyzed numerically. As the result of the simulation, it was calculated that the radioactive metallic waste will be reduced to less than 1/100.

JAEA Reports

Numerical analysis of fractional distillation characteristics for radioactive metallic waste

Akaoka, Katsuaki; Maruyama, Yoichiro

JAERI-Research 2004-012, 12 Pages, 2004/08

JAERI-Research-2004-012.pdf:3.52MB

The fractional distillation characteristics at between 0 $$^{circ}$$C and 2500 $$^{circ}$$C(the rate is 200 $$^{circ}$$C/h) of radioactive metallic waste for JPDR which mainly consists of stainless steel were analyzed numerically. In the simulation, the vaporization rates of the components of JPDR waste were calculated by using the Langmuir's equation and Henry's law. As the results, it was calculated that $$^{152,154}$$Eu, $$^{14}$$C and $$^{94}$$Nb can be removed by the fractional distillation. On the other hand, $$^{54}$$Mn and $$^{55}$$Fe can be reduced by cooling them for about 30 years. Therefore, by removing $$^{59,63}$$Ni and $$^{60}$$Co using laser separation method, it will be possible to reduce the radioactive metallic waste by less than one one-hundredth.

Journal Articles

Fractional distillation characteristics of duralumin

Akaoka, Katsuaki; Maruyama, Yoichiro

Nihon Kinzoku Gakkai-Shi, 68(3), p.181 - 184, 2004/03

 Times Cited Count:0 Percentile:0.01(Metallurgy & Metallurgical Engineering)

For the separation of radionuclide from the radioactive metallic waste generated by the decommissioning of nuclear facilities, a new method combined with the distillation and laser separation is being developed. The characteristics of fractional distillation for duralumin (Aluminum alloy 7075: Al-5.6Zn-2.5Mg-1.6Cu -0.25Cr) are studied experimentally and theoretically for the first step. In the experiment, the duralumin (378.7 mg) is heated to 1773K with the rate of 200K/h and vaporized. The ion current of its components within the vapor is measured using quadrupole mass spectrometer. In the simulation, the vaporization rate of the components from the melt is calculated by using the Langmuir's equation and the Henry's law. The results of the simulation agree well with the experimental ones, and it is indicated that Al, Mg and Zn could be fractionated from duralumin.

JAEA Reports

Research of vacuum distillation for metals; Elemental separation of duralumin

Akaoka, Katsuaki; Maruyama, Yoichiro

JAERI-Research 2003-022, 16 Pages, 2003/10

JAERI-Research-2003-022.pdf:1.56MB

We measured and simulated the characteristics of vacuum distillation for duralumin (Aluminum alloy 7075: Al-5.6Zn-2.5Mg-1.6Cu-0.25Cr). In the experiment, the duralumin (378.7 mg) was heated to 1500$$^{circ}$$C (the rate is 200$$^{circ}$$C/hour) and vaporized. The ion current of components within the vapor using mass spectrometer was measured. In the simulation, the vaporization rate of components within vapor was calculated by using the formula of Langmuir and the law of Raoult. The simulation agreed well with the experiment, and it was found that the group of Al, Cu and Cr, and the group of Mg and Zn could be separated by the vacuum distillation.These results show that the radioactive wastes can be reduced using the vacuum distillation.

Journal Articles

Numerical estimation method of the hydrogen isotope inventory in the hydrogen isotope separation system for fusion reactor

Iwai, Yasunori; Yamanishi, Toshihiko; Nakamura, Hirofumi; Isobe, Kanetsugu; Nishi, Masataka; Willms, R. S.*

Journal of Nuclear Science and Technology, 39(6), p.661 - 669, 2002/06

 Times Cited Count:9 Percentile:53.47(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

A Design stufy of hydrogen isotope separation system for ITER-FEAT

Iwai, Yasunori; Yamanishi, Toshihiko; Nishi, Masataka

JAERI-Tech 2001-027, 29 Pages, 2001/03

JAERI-Tech-2001-027.pdf:1.11MB

no abstracts in English

Journal Articles

Design study of feasible water detritiation systems for fusion reactor of ITER scale

Iwai, Yasunori; Yamanishi, Toshihiko; Okuno, Kenji; Yokogawa, Nobuhisa*; *; Yoshida, Hiroshi; O.K.Kveton*

Journal of Nuclear Science and Technology, 33(12), p.981 - 992, 1996/12

 Times Cited Count:25 Percentile:88.16(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of spent solvent treatment process by submerged combustion technique

Uchiyama, Gunzo; Maeda, Mitsuru; Fujine, Sachio; *; *; *

Journal of Nuclear Science and Technology, 31(3), p.228 - 239, 1994/03

 Times Cited Count:8 Percentile:61.28(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Application of an advanced incineration technique to spent solvent treatment for improving the waste management

Uchiyama, Gunzo; Maeda, Mitsuru; *; Fujine, Sachio; *; *

Proceedings of 4th International Conference on Nuclear Fuel Reprocessing and Waste Management; RECOD '94, Vol.3, 0, p.1 - 15, 1994/00

no abstracts in English

JAEA Reports

Conceptual design study and evaluation of an advanced treatment process applying a submerged combustion technique for spent solvents

Uchiyama, Gunzo; Maeda, Mitsuru; Fujine, Sachio; *; *

JAERI-M 93-213, 204 Pages, 1993/10

JAERI-M-93-213.pdf:6.12MB

no abstracts in English

JAEA Reports

Combustion behavior of spent solvent in a submerged combustion process

Uchiyama, Gunzo; Maeda, Mitsuru; Fujine, Sachio; *; *

JAERI-M 93-191, 58 Pages, 1993/10

JAERI-M-93-191.pdf:2.23MB

no abstracts in English

JAEA Reports

Joint operation of TSTA under the collaboration between JAERI and DOE-LANL; An Integrated loop operation with 100-g tritium in July 1988

Okuno, Kenji; Enoeda, Mikio; *; *; Yoshida, Hiroshi; Naruse, Yuji; Anderson, J. L.*; Bartlit, J. R.*; Sherman, R. H.*; R.V.Carlson*; et al.

JAERI-M 90-028, 73 Pages, 1990/02

JAERI-M-90-028.pdf:1.51MB

no abstracts in English

Journal Articles

Design concept of cryogenic falling liquid film helium separator

; ; J.R.Bartlit*; R.H.Sherman*

Fusion Technology, 10, p.137 - 148, 1986/00

no abstracts in English

Journal Articles

Journal Articles

Drastic reduction of computing time in dynamic simulation for hydrogen isotope distillation columns

Fusion Technology, 9, p.492 - 498, 1986/00

no abstracts in English

25 (Records 1-20 displayed on this page)