A Design study for tritium recovery system from cooling water of a fusion power plant

Yamanishi, Toshihiko; Iwai, Yasunori; Kawamura, Yoshinori; Nishi, Masataka

Fusion Engineering and Design, 81(1-7), p.797 - 802, 2006/02

https://doi.org/10.1016/j.fusengdes.2005.07.023

no abstracts in English

H-D-T cryogenic distillation experiments at TPL/JAERI in support of ITER

Iwai, Yasunori; Yamanishi, Toshihiko; Ohira, Shigeru; Suzuki, Takumi; Shu, Wataru; Nishi, Masataka

Fusion Engineering and Design, 61-62, p.553 - 560, 2002/11

https://doi.org/10.1016/S0920-3796(02)00175-8

no abstracts in English

Experimental investigations of the effect of alkali fluids on montmorillonite, albite and quartz

JNC TN8400 2001-008, 36 Pages, 2001/03

JNC-TN8400-2001-008.pdf:2.92MB

Research on geologic disposal of high-level radioactive waste(HLW) has been underway in many countries. Bentonite exhibiting a low permeability, high swelling property and high sorption capacity for many radioelements is proposed as a buffer material in many countlies. Recently, cementitious materials are considered as candidate matelials for the geologic disposal of high-level radioactive waste. As the pH and the Ca, Na, K contents of hyperalkaline pore water from the cementitious materials are high, this hyperalkaline pore water would alter the buffer material. The main aim of this study is to investigate the effect of alkaline pore water into the bentonite. Used materials are montmorillonite, albite and quartz composing bentonite. These minerals mixed in a constant ratio (1:1wt%) made to react to distilled water and the alkali solutions (pH11-13). These studies have been conducted at temperatures of 50 - 150C and run times of 10 - 200 day. XRD(X-ray powder diffraction) and SEM (Scanning Electron Microscopy) analyses were applied to studying the structure and quantitative data of each sample. From the result of this study, the main formed mineral of this experiment was analcime, which showed the tendency with a large amount of generation at a higher pH and temperature. Quantitative data of this study was conducted by X-ray powder diffraction method. THe order of the amount of the second analcime in each experiment is shown in the following. Montmorillonite and albite mixing test Montmorillonite test Montmorillonite and quartz mixing test Activation energies (E) using the quantitative data of each test are shown in the following. (1)Montmorillonite test : 54.9kJ/mol (2)Montmorillonite and albite mixing test : 51.9kJ/mol (3)Montmorillonite and quartz mixing test : 59.6kJ/mol

Progress of fusion fuel processing system development at the Japan Atomic Energy Research Institute

Nishi, Masataka; Yamanishi, Toshihiko; Kawamura, Yoshinori; Iwai, Yasunori; Isobe, Kanetsugu; Ohira, Shigeru; Hayashi, Takumi; Nakamura, Hirofumi; Kobayashi, Kazuhiro; Suzuki, Takumi; et al.

Fusion Engineering and Design, 49-50, p.879 - 883, 2000/11

https://doi.org/10.1016/S0920-3796(00)00325-2

no abstracts in English

Development of system analysis code for pyrochemical process using molten salt electrorifining

Tozawa, Katsuhiro; ; Kakehi, Isao

JNC TN9400 2000-052, 110 Pages, 2000/04

JNC-TN9400-2000-052.pdf:4.39MB

This report describes accomplishment of development of a cathode processor calculation code to simulate the mass and heat transfer phenomena with the distillation process and development of an analytical model for cooling behavior of the pyrochemical process cell on personal computers. The pyrochemical process using molten salt electrorefining would introduce new technologies for new fuels of particle oxide, particle nitride and metallic fuels. The cathode processor calculation code with distillation process was developed. A code validation calculation has been conducted on the basis of the benchmark problem for natural convection in a square cavity. Results by using the present code agreed well for the velocity-temperature fields, the maximum velocity and its location with the benchmark solution published in a paper. The functions have been added to advance the reality in simulation and to increase the efficiency in utilization. The test run has been conducted using the code with the above modification for an axisymmetric enclosed vessel simulating a cathode processor, and the capability of the distillation process simulation with the code has been confirmed. An analytical model for cooling behavior of the pyrochemical process cell was developed. The analytical model was selected by comparing benchmark analysis with detailed analysis on engineering workstation. Flow and temperature distributions were confirmed by the result of steady state analysis. In the result of transient cooling analysis, an initial transient peak of temperature occurred at balanced heat condition in the steady-state analysis. Final gas temperature distribution was dependent on gas circulation flow in transient condition. Then there were different final gas temperature distributions on the basis of the result of steady-state analysis. This phenomenon has a potential for it's own metastable condition. Therefore it was necessary to design gas cooling flow pattern without ...

Demonstration of the integrated fusion fuel loop at the tritium process laboratory of the Japan Atomic Energy Research Institute

Yamanishi, Toshihiko; Konishi, Satoshi; Hayashi, Takumi; Kawamura, Yoshinori; Iwai, Yasunori; Maruyama, T.*; Kakuta, Toshiya*; Ohira, Shigeru; Nakamura, Hirofumi; Kobayashi, Kazuhiro; et al.

Fusion Technology, 34(3), p.536 - 540, 1998/11

no abstracts in English

Tritium behavior in fusion reactor facilities and the environment, 3; Tritium behavior in fusion fuel systems

Yamanishi, Toshihiko; Nishikawa, Masabumi*; *

Purazuma, Kaku Yugo Gakkai-Shi, 73(12), p.1326 - 1332, 1997/12

https://ci.nii.ac.jp/naid/110003826816

no abstracts in English

Study of column construction and tritium inventory of cryogenic distillation columns for tritium plant of a fusion reactor

Iwai, Yasunori; Yamanishi, Toshihiko; Okuno, Kenji

JAERI-Tech 96-043, 31 Pages, 1996/11

JAERI-Tech-96-043.pdf:0.95MB

no abstracts in English

Development of a fusion fuel processing system at the Japan Atomic Energy Research Institute

Konishi, Satoshi; Enoeda, Mikio; Yamanishi, Toshihiko; Okuno, Kenji

Fusion Technology 1996, 0, p.1221 - 1224, 1996/00

no abstracts in English

Operation of a simulated non-steady tokamak fuel loop using the tritium systems test assembly

Konishi, Satoshi; Yamanishi, Toshihiko; Enoeda, Mikio; Hayashi, Takumi; Ohira, Shigeru; Yamada, Masayuki; Suzuki, Takumi; Okuno, Kenji; Sherman, R. H.*; Willms, R. S.*; et al.

Fusion Engineering and Design, 28, p.258 - 264, 1995/00

https://doi.org/10.1016/0920-3796(94)00238-3

no abstracts in English