Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 25

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Feasibility study of tritium recoil barrier for neutron reflectors

Ishitsuka, Etsuo; Sakamoto, Naoki*

Physical Sciences and Technology, 6(2), p.60 - 63, 2019/12

Tritium release into the primary coolant of the research and test reactors during operation had been studied, and it is found that the recoil release from chain reaction of $$^{9}$$Be is dominant. To reduce tritium concentration of the primary coolant, feasibility study of the tritium recoil barrier for the beryllium neutron reflectors was carried out, and the tritium recoils of various materials were calculated by PHITS. From these calculation results, it is clear that the thickness of tritium recoil barrier depends on the material and 20$$sim$$40 $$mu$$m is required for three orders reduction.

JAEA Reports

Calculations of Tritium Recoil Release from Li and U Impurities in Neutron Reflectors (Joint research)

Ishitsuka, Etsuo; Kenzhina, I.*; Okumura, Keisuke; Ho, H. Q.; Takemoto, Noriyuki; Chikhray, Y.*

JAEA-Technology 2018-010, 33 Pages, 2018/11

JAEA-Technology-2018-010.pdf:2.58MB

As a part of study on the mechanism of tritium release to the primary coolant in research and testing reactors, tritium recoil release rate from Li and U impurities in the neutron reflector made by beryllium, aluminum and graphite were calculated by PHITS code. On the other hand, the tritium production from Li and U impurities in beryllium neutron reflectors for JMTR and JRR-3M were calculated by MCNP6 and ORIGEN2 code. By using both results, the amount of recoiled tritium from beryllium neutron reflectors were estimated. It is clear that the amount of recoiled tritium from Li and U impurities in beryllium neutron reflectors are negligible, and 2 and 5 orders smaller than that from beryllium itself, respectively.

Journal Articles

Radiation-induced thermoelectric sensitivity in the mineral-insulated cable of magnetic diagnostic coils for ITER

Nishitani, Takeo; Vayakis, G.*; Yamauchi, Michinori*; Sugie, Tatsuo; Kondoh, Takashi; Shikama, Tatsuo*; Ishitsuka, Etsuo; Kawashima, Hisato

Journal of Nuclear Materials, 329-333(Part2), p.1461 - 1465, 2004/08

 Times Cited Count:16 Percentile:69.80(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Advanced control scenario of high-performance steady-state operation for JT-60 superconducting tokamak

Tamai, Hiroshi; Kurita, Genichi; Matsukawa, Makoto; Urata, Kazuhiro*; Sakurai, Shinji; Tsuchiya, Katsuhiko; Morioka, Atsuhiko; Miura, Yushi; Kizu, Kaname; Kamada, Yutaka; et al.

Plasma Science and Technology, 6(3), p.2281 - 2285, 2004/06

 Times Cited Count:0 Percentile:0.02(Physics, Fluids & Plasmas)

High performance steady-state operation for JT-60SC are evaluated by the TOPICS analysis. $$beta$$$$_N$$$$sim$$5 and bootstrap current fraction $$sim$$86% is kept steady at I$$_p$$=1.5 MA, B$$_t$$=2 T by neutral beam power of 11 MW. The ERATO-J analysis shows that the external-kink mode with multiple toroidal mode numbers of n=1 and n=2 is stable at $$beta$$$$_N$$ $$leq$$5.5 at the average ratio of conducting wall radius to plasma minor radius of about 1.2 with the wall stabilisation effect. Resistive wall modes, induced by a close location of the wall to plasma, is expected to be suppressed by the active feedback stabilisation with a set of non-axisymmetric field coils behind the stabilising plates. Further optimisation for the high-$$beta$$$$_N$$ accessibility by the plasma shaping is performed with the TOSCA analysis. The plasma shaping factor defined as S=(I$$_p$$/aB$$_t$$)q$$_9$$$$_5$$ and strongly correlated to the plasma elongation and triangularity, is scanned from $$sim$$4 to $$sim$$6, which extends the availability of current and pressure profile control for the high performance plasma operation.

Journal Articles

CS model coil test facility

Kato, Takashi; Nakajima, Hideo; Isono, Takaaki; Hamada, Kazuya; Kawano, Katsumi; Sugimoto, Makoto; Nunoya, Yoshihiko; Koizumi, Norikiyo; Matsui, Kunihiro; Oshikiri, Masayuki*; et al.

Teion Kogaku, 36(6), p.315 - 323, 2001/06

no abstracts in English

Journal Articles

Acoustic emission in ITER CS model coil and CS insert coil

Ninomiya, Akira*; Arai, Kazuaki*; Takano, Katsutoshi*; Nakajima, Hideo; Michael, P.*; Martovetsky, N.*; Takahashi, Yoshikazu; Kato, Takashi; Ishigooka, Takeshi*; Kaiho, Katsuyuki*; et al.

Teion Kogaku, 36(6), p.344 - 353, 2001/06

no abstracts in English

Journal Articles

Supercritical helium pump

Kato, Takashi

Tabo Kikai, 28(9), p.536 - 545, 2000/09

no abstracts in English

JAEA Reports

ITER cryostat main chamber and vacuum vessel pressure suppression system design

; Nakahira, Masataka; Takahashi, Hiroyuki*; Tada, Eisuke; ;

JAERI-Tech 99-026, 158 Pages, 1999/03

JAERI-Tech-99-026.pdf:6.58MB

no abstracts in English

JAEA Reports

Irradiation effects on plasma diagnostic components

Nishitani, Takeo; ; Ikeda, Yujiro; Ishitsuka, Etsuo; Kakuta, Tsunemi; Kasai, Satoshi; Kawamura, Hiroshi; Morita, Yosuke; Nagashima, Akira; Nakamichi, Masaru; et al.

JAERI-Research 98-053, 105 Pages, 1998/10

JAERI-Research-98-053.pdf:4.78MB

no abstracts in English

Journal Articles

Effects of primary recoil (PKA) energy spectrum on radiation damage in FCC metals

Iwata, Tadao; Iwase, Akihiro

Radiat. Eff. Defect Solids, 144(1-4), p.27 - 61, 1998/00

no abstracts in English

Journal Articles

Measurements of the response function and the detection efficiency of an NE213 scintillator for neutrons between 20 and 65 MeV

Meigo, Shinichiro

Nuclear Instruments and Methods in Physics Research A, 401, p.365 - 378, 1997/00

 Times Cited Count:60 Percentile:95.90(Instruments & Instrumentation)

no abstracts in English

Journal Articles

Final design of a cryogenic system for the ITER CS model coil

; ; Kato, Takashi; Kawano, Katsumi; Hiyama, Tadao; ; ; Otsu, K.*; ; Tsuji, Hiroshi

Cryogenics, 34(Suppl.), p.65 - 68, 1994/00

no abstracts in English

Journal Articles

Test results of the DPC-TJ; Mechanical performance

Wachi, Y.*; ; ; ; Fujioka, T.*; Nakajima, Hideo; Sugimoto, Makoto; Koizumi, Koichi; Yoshida, Kiyoshi; ; et al.

Cryogenics, 33(6), p.603 - 608, 1993/00

 Times Cited Count:2 Percentile:17.81(Thermodynamics)

no abstracts in English

Journal Articles

The DPC-TJ program; Development of a high-current-density large superconducting coil for fusion machines

Nishi, Masataka; Ando, Toshinari; Tsuji, Hiroshi; ; Hamajima, Takataro*; Fujioka, T.*

Teion Kogaku, 27(3), p.207 - 216, 1992/00

no abstracts in English

Journal Articles

Test results of the DPC-TJ; Mechanical performance

Wachi, Y.*; ; ; ; Fujioka, T.*; Nakajima, Hideo; Sugimoto, Makoto; Koizumi, Koichi; Yoshida, Kiyoshi; ; et al.

Teion Kogaku, 27(3), p.245 - 251, 1992/00

no abstracts in English

Journal Articles

Test results of the DPC-TJ; Thermal and hydraulic performances

Sugimoto, Makoto; Kato, Takashi; Kawano, Katsumi; Hiyama, Tadao; ; ; ; ; ; Okuno, Kiyoshi; et al.

Teion Kogaku, 27(3), p.239 - 244, 1992/00

no abstracts in English

JAEA Reports

Conceptual design of SC magnet system for ITER, II; Stress analysis

Koizumi, Koichi; Hasegawa, Mitsuru*; Yoshida, Kiyoshi

JAERI-M 91-121, 200 Pages, 1991/08

JAERI-M-91-121.pdf:3.95MB

no abstracts in English

Journal Articles

Recoil tritium reaction in rare gas-ethane solid mixtures at ultralow temperature

K.W.Lee*; ; ; ; ; ; Saeki, Masakatsu; Tachikawa, Enzo

J.Phys.Chem., 90, p.5343 - 5347, 1986/00

no abstracts in English

Journal Articles

350-liter/hour, 1.2kW helium liquefier/refrigerator system

; Hiyama, Tadao; Kato, Takashi; ;

Teion Kogaku, 19(2), p.139 - 152, 1984/00

no abstracts in English

25 (Records 1-20 displayed on this page)