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Journal Articles

Measurements of electron-induced neutrons as a tool for determination of electron temperature of fast electrons in the task of optimization laser-produced plasma ions acceleration

Sakaki, Hironao; Nishiuchi, Mamiko; Maeda, Shota; Sagisaka, Akito; Pirozhkov, A. S.; Pikuz, T.; Faenov, A.*; Ogura, Koichi; Fukami, Tomoyo; Matsukawa, Kenya*; et al.

Review of Scientific Instruments, 85(2), p.02A705_1 - 02A705_4, 2014/02

 Times Cited Count:2 Percentile:11.24(Instruments & Instrumentation)

High intensity laser-plasma interaction has attracted considerable interest for a number of years. The laser-plasma interaction is accompanied by generation of various charged particle beams. Results of simultaneous novel measurements of electron-induced photonuclear neutrons (photoneutron), which are a diagnostic of the laser-plasma interaction, are proposed to use for optimization of the laser-plasma ion generation. The proposed method is demonstrated by the laser irradiation with the intensity os 1$$times$$10$$^{21}$$ W/cm$$^{2}$$ on the metal foil target. The photoneutrons are measured by using NE213 liquid scintillation detectors. Heavy-ion signal is registered with the CR39 track detector simultaneously. The measured signals of the electron-induced photoneutrons are well reproduced by using the Particle and Heavy Ion Transport code System (PHITS). The results obtained provide useful approach for analyzing the various laser based ion beams.

Journal Articles

Development of an extensive database of mechanical and physical properties for reduced-activation martensitic steel F82H

Jitsukawa, Shiro; Tamura, Manabu*; Van der Schaaf, B.*; Klueh, R. L.*; Alamo, A.*; Petersen, C.*; Schirra, M.*; Spaetig, P.*; Odette, G. R.*; Tavassoli, A. A.*; et al.

Journal of Nuclear Materials, 307-311(Part1), p.179 - 186, 2002/12

 Times Cited Count:160 Percentile:99.28(Materials Science, Multidisciplinary)

Reduced activation ferritic/martensitic steel is the primary candidate structural material for ITER Test Blanket Modules and DEMOnstration fusion reactor because of its excellent dimensional stability under irradiation and lower residual activity as compared with the Ni bearing steels such as the austenitic stainless steels. In this paper, microstructural features, tensile, fracture toughness, creep and fatigue properties of a reduced activation martensitic steel F82H (8Cr-2W-0.04Ta-0.1C) are reported before and after irradiation, in addition to the design concept used for development of this alloy. A large number of collaborative test results including those generated under the IEA working group implementing agreements are collected and are used to evaluate the feasibility of use of F82H steel as one of the reference alloys. The effect of metallurgical variables on the irradiation hardening is reviewed and compared with the results obtained from irradiation experiments.

JAEA Reports

None

; ; ; ; ; ;

PNC TN9410 95-270, 414 Pages, 1995/10

PNC-TN9410-95-270.pdf:9.47MB

None

JAEA Reports

None

; ; ; Yasu, Tetsunori; ; Terano, Toshihiro;

PNC TN9410 95-269, 458 Pages, 1995/10

PNC-TN9410-95-269.pdf:10.14MB

None

JAEA Reports

Operation experience report of experimental fast reactor JOYO; Operation expelience of primary main and auxiliary cooling systems of JOYO

Karube, Koji; ; ; ; Kawai, Masashi;

PNC TN9440 93-012, 83 Pages, 1993/04

PNC-TN9440-93-012.pdf:5.27MB

This report describes the operating experience of the primary main cooling system from January 1982 to March 1992, and of the primary auxiliary cooling system from october 1986 to March 1992. 0ut lines of the operating experience ale followings; There have been no serious troubles in this period. (1)The main system; Operation time of the circulation pumps are about 67675 hours. Accumulated operation time of the pumps are about 105970 hours. The pumps has been started 212 times. (2)The auxiliary system; Operation time of the circulation pump (EMP) is about 4767 hours. Accumulated operation time of the pump is about 8667 hours. The pump has been automatically started 31 times with the scheduled test.

Journal Articles

Development of PC-based level-1 PSA program package

Watanabe, Norio; *; *; *

Dai-6-Kai Kakuritsuronteki Anzen Hyoka (PSA) Ni Kansuru Kokunai Shimpojiumu Rombunshu (IAE-9206), p.159 - 164, 1993/01

no abstracts in English

Journal Articles

Alloy preparation for studying the effect of hydrogen production during neutron irradiation using $$^{54}$$Fe isotope

Suzuki, Masahide; Hishinuma, Akimichi; *; *; A.F.Rowcliffe*

Journal of Nuclear Materials, 191-194, p.1056 - 1059, 1992/00

 Times Cited Count:4 Percentile:41.92(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Effect of Cr phase on high temperature creep resistance of a 30Cr-50Ni-2Mo alloy

*; *; *; *; *; *

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku 29(2), p.265 - 273, 1988/00

no abstracts in English

JAEA Reports

Research and Development of Austenitic Stainless Steels for Fusim Reactor

Shiraishi, K.; *; *; *; *; *; *; *; *; *; et al.

JAERI-M 84-189, 220 Pages, 1984/09

JAERI-M-84-189.pdf:14.7MB

no abstracts in English

JAEA Reports

Analytical Evaluation of the Environment Effect on Creep Rupture Strength

*; Ogawa, Yutaka; ; Kondo, Tatsuo

JAERI-M 82-036, 18 Pages, 1982/04

JAERI-M-82-036.pdf:0.9MB

no abstracts in English

JAEA Reports

On the Estimation of Long Term Creep Rupture Strength of Hastelloy XR in HTGR Helium Environment

*; Ogawa, Yutaka; ; Kondo, Tatsuo

JAERI-M 82-032, 16 Pages, 1982/04

JAERI-M-82-032.pdf:0.97MB

no abstracts in English

JAEA Reports

New Iron Base Heat Resisting Steels for Application in High Temperature Gas-Cooled Reactor

*; Kondo, Tatsuo

JAERI-M 82-030, 31 Pages, 1982/04

JAERI-M-82-030.pdf:1.79MB

no abstracts in English

JAEA Reports

Effect of Mechanical Surface Treatment on Oxidation and Carburization of some Austenitic Heat Resisting Alloys in the Simulated HTGR Helium Environment

Tamura, Manabu*; Kondo, Tatsuo

JAERI-M 9948, 27 Pages, 1982/02

JAERI-M-9948.pdf:1.49MB

Influence of mechanical surface finishing on corrosion was studied with some austenitic heat resisting alloys exposed to the simulated HTGR helium environment. The exposure tests were made at 900 and 1000$$^{circ}$$C for 500 and 1500h. Contrary to the prediction based on the trend of some conventional experimental results on the oxidation of cold worked material at comparatively low temperatures, severe cold working, e.g. shot-blasting, was found to accelerate oxidation and carburization. Although, in some cases, moderate surface grinding showed results almost comparable to the surface abraded with fine emery papers, most mechanical surface finishing were recognized as to promote oxidation and carburization at 900 and 1000 $$^{circ}$$C in the simulated HTGR helium. The oxide film formed on the ground or shot-blasted specimen tended to spall more easily during cooling after isothermal exposure at 1000$$^{circ}$$C. Based on the metallographic observation mechanisms of the acceleration of oxidation and carburization was discussed. The surface cold work was considered to cause not only enhanced chromium diffusion to the surface but also considerable degree of inhomogeneity of the degree of working in the microscopic scale, resulting in rather rapid oxide build-up and spallation. Some of the surface finishing in practice with severe cold working, thus, were concluded to be harmful to the integrity of HTGR structural components.

Oral presentation

Clarification of creep mechanism of dual phase 9Cr-ODS steel as a composite material

Sakasegawa, Hideo; Otsuka, Satoshi; Ukai, Shigeharu; Tanigawa, Hiroyasu; Ogiwara, Hiroyuki*; Tamura, Manabu*; Koyama, Akira*; Fujiwara, Masayuki*

no journal, , 

Clarifying creep mehcanism of 9Cr-ODS(9Cr-2W-0.2Ti-Y203) steels to be applied for cladding materials in fast breeder reactors are performed in order to improve mass production material processing procedures and the method of creep life prediction. Conventional studies on microstructures in 9Cr-ODS steels revealed that superior creep properties were due to the dual phase structure, delta-ferrite and tempered martensite. Delta ferrite has very fine oxide particles dispersed in the matrix. In this study, the role of delta-ferrite dual phase 9Cr-ODS steel creep mechanism as a compsite material were studied.

Oral presentation

Creep mechanism of 9Cr ODS steel

Sakasegawa, Hideo; Ukai, Shigeharu*; Tamura, Manabu*; Otsuka, Satoshi; Tanigawa, Hiroyasu; Ogiwara, Hiroyuki; Koyama, Akira*; Fujiwara, Masayuki

no journal, , 

no abstracts in English

Oral presentation

Current status of extreme environment single crystal neutron diffractometer SENJU, and latest news from JRR-3

Kaneko, Koji; Ohara, Takashi; Kiyanagi, Ryoji; Kawasaki, Takuro; Oikawa, Kenichi; Tamura, Itaru; Yamauchi, Yasuhiro; Hanashima, Takayasu*; Moyoshi, Taketo*; Nakao, Akiko*; et al.

no journal, , 

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