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Journal Articles

Electronic structures of ultra-thin silicon carbides deposited on graphite

Baba, Yuji; Sekiguchi, Tetsuhiro; Shimoyama, Iwao; Nath, K. G.

Applied Surface Science, 234(1-4), p.246 - 250, 2004/07

 Times Cited Count:10 Percentile:46.84(Chemistry, Physical)

no abstracts in English

Journal Articles

Novel instrument system for discriminating secondary particles in high-spatial-resolution neutron detection

Yamagishi, Hideshi; Nakamura, Tatsuya; Soyama, Kazuhiko; Masaoka, Sei; Aizawa, Kazuya

Review of Scientific Instruments, 75(7), p.2340 - 2345, 2004/07

 Times Cited Count:9 Percentile:46.07(Instruments & Instrumentation)

A new instrument system with the capability of secondary-particle discrimination (InSPaD) was studied for the development of two-dimensional neutron detectors (2D-ND) filled with helium-3 gas and with high spatial resolution. The InSPaD can discriminate between the tracks of a proton and a triton created in the nuclear reaction $$^{3}$$He(${it n}$,${it p}$)${it T}$ by simply setting the level of discriminators appropriately in each signal channel, and the system exhibits a high spatial resolution, high counting rate, low background, and stability. The simulations of the 2D-ND equipped with the InSPaD revealed spatial resolutions of 0.46 mm in full width at half maximum for a 10% mixture of C$$_{2}$$H$$_{6}$$ with helium-3 at 0.3 MPa. The results of neutron-detection experiments using a microstrip gas chamber, including the range of the secondary particles and the pulse-height distribution, agreed well with the simulated results, indicating the feasibility of the InSPaD.

JAEA Reports

Development of micro-strip gas chamber for neutron scattering; Development and simulation of encode board

Masaoka, Sei; Nakamura, Tatsuya; Yamagishi, Hideshi; Soyama, Kazuhiko

JAERI-Research 2003-012, 14 Pages, 2003/06

JAERI-Research-2003-012.pdf:1.58MB

A micro-strip gas chamber (MSGC) using helium-3 gas has been developing as a two-dimensional position sensitive neutron detector for neutron scattering experiments in a high-intensity proton accelerator facility. We have developed the encode board that have built-in FPGAs (Field-Programmable Gate Array). Logics of FPGAs can be freely programmed to carry out digital processing of signals from MSGC and information of the tracks of protons and tritons can be obtained by the encode board. Therefore, the position of neutron capture (more properly the centra of the track) can be calculated by a series of data handling system. As the result of the simulation of a neutron detection experiment, it has proved that the position resolution of less than 1.6 mm can be obtained by using this data handling system.

Journal Articles

A SrBPO$$_{5}$$:Eu$$^{2+}$$ storage phosphor for neutron imaging

Sakasai, Kaoru; Katagiri, Masaki; To, Kentaro; Takahashi, Hiroyuki*; Nakazawa, Masaharu*; Kondo, Yasuhiro*

Applied Physics A, 74(Suppl.1), p.S1589 - S1591, 2002/12

 Times Cited Count:30 Percentile:71.8(Materials Science, Multidisciplinary)

A phosphor material such as SrBPO$$_{5}$$:Eu$$^{2+}$$ has been investigated for two-dimensional imaging for pulsed-neutron source. The authors found this phosphor itself shows photostimulated luminescence (PSL) by illumination of 635 nm laser light after neutron irradiation without adding any neutron sensitive materials such as Gd. The PSL intensity per neutron flux was proportional to E$$^{-0.5}$$, where E is neutron energy. The neutron sensitivity was increased by using enriched boron instead of natural boron. The S$$_{gamma}$$/S$$_{n}$$ ratio of this phosphor using enriched boron was better than that of a commercially available imaging plate, where S$$_{gamma}$$ and S$$_{n}$$ are gamma and neutron sensitivities, respectively.

Journal Articles

Water experiment of high-speed, free-surface, plane jet along concave wall

Nakamura, Hideo; *; Kukita, Yutaka*; *; ; Maekawa, Hiroshi

Eighth Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), 3, p.1268 - 1275, 1997/00

no abstracts in English

Journal Articles

Loss-of-coolant accident analysis for ITER divertor system

Yonomoto, Taisuke; Kukita, Yutaka; Ogawa, Masuro; Kunugi, Tomoaki; Seki, Yasushi; *; Takatsu, Hideyuki

Proc. of the 6th Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics,Vol. 2, p.807 - 814, 1993/00

no abstracts in English

JAEA Reports

Effects of radial core power profile on core thermo-hydraulic behavior during reflood phase in SCTF core-I forced feed tests

Iwamura, Takamichi; *; Sudo, Yukio; Sobajima, Makoto; Onuki, Akira; Abe, Yutaka; *; Murao, Yoshio

JAERI-M 91-093, 89 Pages, 1991/06

JAERI-M-91-093.pdf:1.87MB

no abstracts in English

JAEA Reports

Comparison of facility characteristics between SCTF core-I and core-II

*; Iwamura, Takamichi; Sobajima, Makoto; Onuki, Akira; Abe, Yutaka; Murao, Yoshio

JAERI-M 90-130, 77 Pages, 1990/08

JAERI-M-90-130.pdf:1.72MB

no abstracts in English

JAEA Reports

Cold leg injection reflood test results in the SCTF core-1 under constant system pressure

Adachi, Hiromichi; Iwamura, Takamichi; Sobajima, Makoto; ; Onuki, Akira; Abe, Yutaka; Murao, Yoshio

JAERI-M 90-129, 179 Pages, 1990/08

JAERI-M-90-129.pdf:3.71MB

no abstracts in English

JAEA Reports

Development of SCTF cold leg injection test method for eliminating U-tube oscillation during the initial period

Adachi, Hiromichi; Iwamura, Takamichi; Sobajima, Makoto; Onuki, Akira; Abe, Yutaka; Okubo, Tsutomu; Murao, Yoshio

JAERI-M 90-107, 146 Pages, 1990/07

JAERI-M-90-107.pdf:2.89MB

no abstracts in English

Journal Articles

Pressure loss of single-phase slanting cross flow in rod bundle

Osakabe, Masahiro

Journal of Nuclear Science and Technology, 24(6), p.498 - 500, 1987/06

 Times Cited Count:0 Percentile:0.43(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Heat transfer enhancement in SCTF tests

; ; ; ; ; Abe, Yutaka; Murao, Yoshio

NUREG/CP-0082 Vol.4, p.429 - 444, 1987/00

no abstracts in English

JAEA Reports

Development of Coupled Nuclear-Thermal Caluclation Code System

*; *; ; *; *

JAERI-M 86-084, 32 Pages, 1986/06

JAERI-M-86-084.pdf:0.75MB

no abstracts in English

Journal Articles

Experimental study of two-dimensional thermal-hydraulic behavior in core during reflood phase of PWR LOCA

; ;

Journal of Nuclear Science and Technology, 23(2), p.123 - 135, 1986/00

 Times Cited Count:4 Percentile:48.02(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Journal Articles

Five percent break BWR LOCA/ECC test at ROSA-III without HPCS actuation; Two dimensional core thermal-hydraulic phenomena

; Koizumi, Yasuo; Tasaka, Kanji

Nucl.Eng.Des., 86, p.219 - 239, 1985/00

 Times Cited Count:2 Percentile:37.51(Nuclear Science & Technology)

no abstracts in English

35 (Records 1-20 displayed on this page)