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Kudo, Atsunari; Kurabayashi, Kazuaki; Yanagibashi, Futoshi; Sasaki, Shunichi; Sato, Takehiko; Fujimoto, Ikuo; Obu, Tomoyuki
Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 6 Pages, 2017/04
The Co-processing process is the extraction process to recover Pu/U mixed product solution with given Pu/U ratio for improving of nuclear proliferation resistance. In addition, Np is also recovered with U and Pu because Np is one of minor actinides and a long-lived radionuclide and Np has the extractability into TBP solvent. Development of its flowsheet achieves to decrease environmental effect of waste materials. The orientation of development about Co-processing process is to demonstrate of reprocessing the future spent fuels from a LWR, a LWR-MOX hybrid, and a FR-MOX with one cycle. We demonstrated by use of miniature reflux-type centrifugal contactors at the partitioning unit. The test conditions of the Pu/U ratio in the loaded solvents were 1%, 3%, and 5% considering the composition of spent fuels. We used the HAN as the reductant of Np (VI) for back extraction. The results of these tests were very good. We got the prospect of U, Pu, and Np Co-processing flowsheet.
Iwai, Yasunori; Yamanishi, Toshihiko; Hayashi, Takumi; Nishi, Masataka
Fusion Science and Technology, 48(1), p.456 - 459, 2005/07
Times Cited Count：3 Percentile：24.17(Nuclear Science & Technology)Addition of gas separation membrane process into usual tritium removal process from atmosphere in a room is attractive for fusion plants where a large amount of atmosphere should be processed. Therefore, the gas separation membrane has been studied. New concept of membrane separation with reflux flow is proposed in the present. Driving force of membrane separation is the difference of partial pressure through membrane. Hence, reflux of a part of gases at permeated side to feed side enhances driving force. Essential points of present discussion are as follows: (1) Reflux has plus effect of driving force enhancement and minus effect of feed flow increase, hence, there is the optimum. (2) Permeated-side pressure effects enhancement of tritium recovery strongly. (3) Effect of reflux becomes striking as the target species have higher permeability coefficient, therefore, it is favorable for tritium recovery because those of hydrogen gas and water vapor are much higher among atmosphere elements. In addition, application of reflux flow will realize scale reduction of expensive membrane module.
Arita, Tadaaki*; Yamanishi, Toshihiko; Iwai, Yasunori; Nishi, Masataka; Yamamoto, Ichiro*
Fusion Science and Technology, 41(3), p.1116 - 1120, 2002/05
no abstracts in English
Koshizuka, Seiichi*
JNC TJ9400 2000-011, 102 Pages, 2000/03
JNC-TJ9400-2000-011.pdf:2.71MB
In order to evaluate the possibility to achieve high electric power by a fast reactor with supercritical light water, the design study was carried out on a large fast reactor core with high coolant outlet temperature (SCFR-H). Since the reactor coolant circuit uses once-through direct cycle where all feedwater flows through the core to the turbine at supercritical pressure, it is possible to design much simpler and more compact reactor systems and to achieve higher thermal efficiency than those of current light water reactors. The once-through direct cycle system is employed in current fossil-fired power plants. In the present study, three types of core were designed. The first is SCFR-H with blankets cooled by ascending flow, the second is SCFR-H with blankets cooled by descending flow and the third is SCFR-H with high thermal power. Every core was designed to achieve the thermal efficiency over 43%, positive coolant density reactivity coefficient and electric power over 1600MW. Core characteristics of SCFR-Hs were compared with those of SCLWR-H (electric power: 1212MW), which is a thermal neutron spectrum reactor cooled and moderated by supercritical light water, with the same diameter of the reactor pressure vessel. It was shown that SCFR-H could increase the electric power about l.7 times maximally. From the standpoint of the increase of a reactor thermal power, a fast reactor has advantages as compared with a thermal neutron reactor, because it can increase the power density by adopting tight fuel lattices and eliminating the moderator region. Thus, it was concluded that a reactor cooled by supercritical light water could further improve the cost competitiveness by using a fast neutron spectrum and achieving a higher thermal power.
; Toyama, Shinichi; Nomura, Masahiro; Hirano, Koichiro; Yamazaki, Yoshio; Sato, Isamu
JNC TN9400 99-073, 18 Pages, 1999/08
A short traveling wave accelerator with a traveling wave resonant ring is proposed for high beam current accelerators (including the linear accelerator, circular accelerator and storage ring). It is a normal conducting accelerator. The CW beam current can be as high as 10A. Such kind of accelerator unit has large beam holes for damping all of the cavity high order modes in order to avoid the resonant buildup of the fields that would cause multibunch instabilities at high currents. It has high efficiency, high power input capability and low K
. It is called "single mode" type. Even though beams are accelerated off the crest for phase stability in circular accelerator, the cavities do not need detuning.
Yamanishi, Toshihiko; Okuno, Kenji
Fusion Technology, 28(3), p.1597 - 1602, 1995/10
no abstracts in English
; *; Kubota, Masumitsu
Journal of Radioanalytical and Nuclear Chemistry, 177(2), p.301 - 309, 1994/00
Times Cited Count：12 Percentile：71.34(Chemistry, Analytical)no abstracts in English
Wang, Y.
PNC TN9410 93-203, 57 Pages, 1993/03
The characteristics of TWRR are analysed in detail. They include effects of therefltion, coupling coefficient and directivity. The characteristics of TWRR with anaccerator section are studied.They include analyses of constant impedance structure, witfixed coupling and optimal coupling, and on/off beam loading. Thecharacteristics of nstant gradient structure are also analysed. Q values of TWRR and TWRR with an accelator section are calculated. TWRRs with RF window and with an accelerator section areested in low power and high power. Some phenomena appeared are mentioned and analysedhe stability of TWRR with an accelerator section is discussed.The results of tests sw that the measured parameters of TWRR with an accelerator section are in very good reement with the calculated values.
*; ; Yamaguchi, Isoo; Kubota, Masumitsu
JAERI-M 93-010, 38 Pages, 1993/02
no abstracts in English
Wang, Y.
PNC TN9410 92-039, 26 Pages, 1992/02
A test CW electron linac is designed to develop a high power accelerator to treat waste radioactive material. The linac is to be operated at the room temperature and is energized by two 1.2MW CW L-band klystrons to produce an electron beam with the energy of 10MeV and current of 100mA. The average beam power is 200KW-1MW for the duty factor 20%-100%. In designing such high power electron linear accelerator, an accelerating section having a traveling wave resonant ring is adopted. By adopting such type of acceleration section, it became possible to choose very short length of the accelerator sections to elevate the threshold current of beam break-up (BBU) keeping the high accelerator efficiency. In designing the linac with the traveling wave resonant ring, some special considerations and calculations are introduced. The variational method is used to calculate the sizes and parameters of the disk-loaded accelerator structure. There is the discrepancy of the order of a few hundredth of one percent between the calculated frequency and the experimental one. A kind of internal cooling water structure is adopted to disperse the generated heat by RF efficiently. Currently, its components development is in progress at OEC.
;
Journal of Nuclear Science and Technology, 21(1), p.61 - 70, 1984/00
Times Cited Count：12 Percentile：75.07(Nuclear Science & Technology)no abstracts in English
; ; Naruse, Yuji; Tanaka, Kichizo
Journal of Nuclear Science and Technology, 18(7), p.525 - 539, 1981/00
Times Cited Count：11 Percentile：78.09(Nuclear Science & Technology)no abstracts in English
; Naruse, Yuji
Journal of Nuclear Science and Technology, 18(8), p.595 - 607, 1981/00
Times Cited Count：10 Percentile：75.8(Nuclear Science & Technology)no abstracts in English
; ; Saito, Keiichiro; ; Naruse, Yuji
JAERI-M 8527, 49 Pages, 1979/11
no abstracts in English
; ; Saito, Keiichiro; ; Naruse, Yuji
JAERI-M 8374, 50 Pages, 1979/08
no abstracts in English
Kudo, Atsunari; Yanagibashi, Futoshi; Hoshi, Takahiro; Tada, Kazuhito; Sato, Takehiko; Fujimoto, Ikuo; Obu, Tomoyuki
no journal, ,
no abstracts in English
Kudo, Atsunari; Kurabayashi, Kazuaki; Yanagibashi, Futoshi; Sato, Takehiko; Fujimoto, Ikuo; Obu, Tomoyuki
no journal, ,
no abstracts in English
Kudo, Atsunari; Nagaoka, Shinichi; Kurabayashi, Kazuaki; Yanagibashi, Futoshi; Obu, Tomoyuki
no journal, ,
no abstracts in English
