Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 34

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

Technical estimation for mass production of highly-concentrated $$^{rm 99m}$$Tc solution from $$^{99}$$Mo to be obtained by ($$n,gamma$$) reaction; A Preliminary study using inactive Re instead of $$^{rm 99m}$$Tc

Tanase, Masakazu*; Fujisaki, Saburo*; Ota, Akio*; Shiina, Takayuki*; Yamabayashi, Hisamichi*; Takeuchi, Nobuhiro*; Tsuchiya, Kunihiko; Kimura, Akihiro; Suzuki, Yoshitaka; Ishida, Takuya; et al.

Radioisotopes, 65(5), p.237 - 245, 2016/05

no abstracts in English

Journal Articles

Numerical simulation of melt-down behavior in SFR severe accidents by the MUTRAN code

Kubota, Ryuzaburo*; Yamada, Yumi*; Koyama, Kazuya*; Shimakawa, Yoshio*; Yamano, Hidemasa; Kubo, Shigenobu; Suzuki, Toru; Tobita, Yoshiharu

Proceedings of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-8) (USB Flash Drive), 8 Pages, 2012/12

This paper describes a melt-down event progression revealed by a numerical simulation in the protected loss of heat sink (PLOHS) event for Japan Sodium-cooled Fast Reactor (JSFR). A multi-component multi-field computer code, MUTRAN, has been applied in order to simulate complicated core material motions and associated heat-transfer phenomena among the materials in a degradation core. The analyses with MUTRAN covered core degradation behaviors from the intact geometry and addressed the two initial states: one was the core without the coolant as the leakage type, and the other was the core covered by the coolant only up to the top of the fissile fuel as the boiling type. The analyses revealed representative event progression.

Journal Articles

Transportation of the DTL/SDTL for the J-PARC

Ito, Takashi; Asano, Hiroyuki; Morishita, Takatoshi; Yamazaki, Yoshishige; Naito, Fujio*; Takasaki, Eiichi*; Yoshino, Kazuo*; Tanaka, Hirokazu*; Kato, Takao*; Kabeya, Zenzaburo*; et al.

Proceedings of 23rd International Linear Accelerator Conference (LINAC 2006) (CD-ROM), p.782 - 784, 2007/00

Three DTL tanks and 32 SDTL tanks for the Japan Proton Accelerator Research Complex (J-PARC) were assembled at KEK site. After the assembling, the high-power conditioning of the DTL1 and 12 SDTL tanks and the beam acceleration test for the DTL1 ware carried out. And then all the DTL and SDTL tanks have to be transported form KEK to JAEA. In order to confirm the effect of the transportation to the drift tube alignment, we measured the displacement of the drift tube positions before and after the transportation by using a prototype cavity. As a result of the test, the measured displacement of the drift tubes by the transportation was less than 0.02mm which is consistent in the measurement accuracy. Based on this result, all the DTL and SDTL tanks were transported form KEK to JAEA.

Journal Articles

Tensile and fatigue strength of a through-wall-electron-beam-welded joint for the vacuum vessel of a fusion reactor

Suzuki, Takayuki*; Usami, Saburo*; Kimura, Takae*; Koizumi, Koichi; Nakahira, Masataka; Takahashi, Hiroyuki*

Proceedings of 55th Annual Assembly of International Institute of Welding (IIW2002), 16 Pages, 2002/06

A new type of welded joint for the outer wall and rib of a double-walled vacuum vessel of a fusion reactor has been developed. The joint is manufactured by through-wall electron-beam welding (TW-EBW), in which the beam is injected from the outside of the outer wall. Static and fatigue tests are carried out on one-bead-specimens under an axial load and two-bead-specimens under a bending load. The experimental results are analytically investigated by FEM. Although this joint is partially penetrated, the net yield strength of the bead is increased by the plastic constraint due to triaxial tensile stress in the weldment. This phenomenon reduces the mean equivalent stress on the bead cross section, and the gross strength of the joint is close to that of a full thickness welded joint. The fatigue-strength reduction factor for low-cycle fatigue life is a little larger than four. The calculated fatigue-crack growth rate in the joint is conservatively calculated by using the maximum stress intensity factor of the crack and the fatigue-crack growth rate given in ASME Code Section XI.

JAEA Reports

High temperature corrosion of iron-base and nickel-base alloys for hydrogen production apparatus by thermochemical method in H$$_{2}$$O+SO$$_{3}$$ atmosphere

Kurata, Yuji; Suzuki, Tomio; Shimizu, Saburo

JAERI-Research 2000-011, p.56 - 0, 2000/03

JAERI-Research-2000-011.pdf:14.24MB

no abstracts in English

Journal Articles

Fabrication of the first-loading-fuel of the High Temperature engineering Test Reactor

Sawa, Kazuhiro; Tobita, Tsutomu*; Mogi, Haruyoshi; Shiozawa, Shusaku; Yoshimuta, Shigeharu*; Suzuki, Shuichi*; *

Journal of Nuclear Science and Technology, 36(8), p.683 - 690, 1999/08

 Times Cited Count:32 Percentile:88.99(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Critical review and discussion on HENDEL demonstration tests for HTTR heat utilization systems

Hino, Ryutaro; Suzuki, Kunihiro; Haga, Katsuhiro; Nekoya, Shinichi; Fukaya, Kiyoshi; Shimizu, Saburo; Onuki, Kaoru; Takada, Shoji; Mogi, Haruyoshi; Sudo, Yukio

JAERI-Review 95-016, 115 Pages, 1995/10

JAERI-Review-95-016.pdf:3.5MB

no abstracts in English

Journal Articles

None

; Yamada, Keiji; ; Ikeda, Hisashi ; Kuno, Yusuke

Donen Giho, (94), p.91 - 94, 1995/06

None

Journal Articles

Overview of piping reliability test program at the Japan Atomic Energy Research Institute

Isozaki, Toshikuni; Shibata, Katsuyuki; *; Ueda, Shuzo; Kurihara, Ryoichi

Transactions of the 11th Int. Conf. on Structural Mechanics in Reactor Technology, Vol. SDO, p.401 - 412, 1991/08

no abstracts in English

JAEA Reports

Data report for ROSA-IV LSTF 10% hot leg break experiment Run SB-HL-04

Kukita, Yutaka; Nakamura, Hideo; *; *; *; Anoda, Yoshinari; Kumamaru, Hiroshige; Suzuki, Mitsuhiro; ; Yonomoto, Taisuke; et al.

JAERI-M 91-040, 122 Pages, 1991/03

JAERI-M-91-040.pdf:3.42MB

no abstracts in English

Journal Articles

Programmed temperature control of capsule in irradiation test with personal computer at JMTR

; Uramoto, Toshimasa; Fukushima, Masao; ; ; ;

Proc. of the 3rd Asian Symp. on Research Reactor, p.285 - 292, 1991/00

no abstracts in English

JAEA Reports

Data report for ROSA-IV LSTF 10% hot leg break experiment; Run SB-HL-02

Kukita, Yutaka; *; *; *; Anoda, Yoshinari; Kumamaru, Hiroshige; Suzuki, Mitsuhiro; ; Yamamoto, Nobuo; Nakamura, Hideo; et al.

JAERI-M 90-039, 122 Pages, 1990/03

JAERI-M-90-039.pdf:3.38MB

no abstracts in English

JAEA Reports

Data report for ROSA-IV/LSTF 5% hot leg break experiment Run SB-HL-01

Kukita, Yutaka; *; *; Anoda, Yoshinari; Kumamaru, Hiroshige; Suzuki, Mitsuhiro; ; Yamamoto, Nobuo; Nakamura, Hideo; Yonomoto, Taisuke; et al.

JAERI-M 89-225, 117 Pages, 1990/01

JAERI-M-89-225.pdf:3.53MB

no abstracts in English

JAEA Reports

Data report for ROSA-IV LSTF 5% cold leg break LOCA experiment Run SB-CL-08

Kukita, Yutaka; *; *; Anoda, Yoshinari; Kumamaru, Hiroshige; Suzuki, Mitsuhiro; ; Yamamoto, Nobuo; Nakamura, Hideo; Yonomoto, Taisuke; et al.

JAERI-M 89-220, 127 Pages, 1990/01

JAERI-M-89-220.pdf:3.57MB

no abstracts in English

JAEA Reports

ROSA-IV/LSTF 5% cold leg break LOCA experiment Run SB-CL-18 data report

Kumamaru, Hiroshige; *; Nakamura, Hideo; Kukita, Yutaka; Koizumi, Yasuo; Anoda, Yoshinari; Suzuki, Mitsuhiro; ; Katayama, Jiro; Yamamoto, Nobuo; et al.

JAERI-M 89-027, 105 Pages, 1989/03

JAERI-M-89-027.pdf:2.8MB

no abstracts in English

JAEA Reports

Underwater plasma arc cutting of in-reactor tube of in-pile creep test facility

; ; ; *; ; Itami, Hiroharu

JAERI-M 88-199, 39 Pages, 1988/10

JAERI-M-88-199.pdf:2.28MB

no abstracts in English

JAEA Reports

JAEA Reports

Test and research ice-blasting equipment, II

Nishimoto, Wataru*; Kimuro, Harumi*; Ishibashi, Seijiro*; Miyahara, Shuji*; Yamashita, Saburo*; Hayashi, Mitsuo*; Suzuki, Yoji*; Hirose, Yasuo*

PNC TJ118 85-06VOL2, 221 Pages, 1985/04

PNC-TJ118-85-06VOL2.pdf:20.84MB

None

JAEA Reports

Test and research of Ice-Blasting equipment, II

Nishimoto, Wataru*; Kimuro, Harumi*; Ishibashi, Seijiro*; Miyahara, Shuji*; Yamashita, Saburo*; Hayashi, Mitsuo*; Suzuki, Yoji*; Hirose, Yasuo*

PNC TJ118 85-06VOL1, 21 Pages, 1985/04

PNC-TJ118-85-06VOL1.pdf:1.04MB

no abstracts in English

JAEA Reports

ROSA-IV Large Scale Test Facility(LSTF)System Description

*; Tasaka, Kanji; ; ; ; Koizumi, Yasuo; ; ; ; ; et al.

JAERI-M 84-237, 300 Pages, 1985/01

JAERI-M-84-237.pdf:7.57MB

no abstracts in English

34 (Records 1-20 displayed on this page)