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Journal Articles

Neutron spectra and angular distributions of concrete-moderated neutron calibration fields at JAERI

Yoshizawa, Michio; Tanimura, Yoshihiko; Saegusa, Jun; Nemoto, Hisashi*; Yoshida, Makoto

Radiation Protection Dosimetry, 110(1-4), p.81 - 84, 2004/09

 Times Cited Count:3 Percentile:23.52(Environmental Sciences)

The facility of Radiation Standards (FRS) of JAERI has equipped with the concrete-moderated neutron calibration fields as simulated workplace neutron fields. The fields use an Am-Be (37GBq) neutron source placed in the narrow space surrounded by concrete wall and bricks to produce scattered neutrons. The neutron spectra of the fields were measured with Bonner multi-sphere spectrometer system (BMS), spherical recoil-proton proportional counters (RPCs), and a liquid scintillation counter (NE-213). The results were compared with each other, and the neutron spectra and the ambient dose equivalent rate, ${it H}$$$^{*}$$(10), were agreed well within the uncertainty. The angular distributions of neutron fluence were calculated by the MCNP-4B2 Monte Carlo code to obtain the reference personal dose equivalent rate, ${it H}$$$_{p}$$(10). The calculated results show that the scattered neutrons have a wide variety of incident angles. The reference ${it H}$$$_{p}$$(10) values considered the angular distribution were found to be 10-18% smaller than those without consideration.

JAEA Reports

Experimental study on sequential reactions in fusion reactor materials by D-T neutron irradiation

Hori, Junichi; Sato, Satoshi; Yamauchi, Michinori*; Ochiai, Kentaro; Nishitani, Takeo

JAERI-Research 2003-002, 50 Pages, 2003/03

JAERI-Research-2003-002.pdf:2.21MB

D-T neutron irradiation experiments have been performed with F82H and ODS ferritic steels and the effective cross sections for $$^{56}$$Co productions in those materials via the sequential reactions were measured. The effective cross sections for F82H and ODS ferritic steels were about 1.5 times larger than that for iron. The distributions of effective cross sections were measured for 6 materials (iron, copper, vanadium, titanium, tungsten and lead) and F82H. The sequential reaction rates in the region close to hydrogen compound became over 20 times larger than that in material itself. In the case of F82H, the increase ratio was about 50. It was indicated that the activity for the sequential reaction product $$^{56}$$Co will reach to 3-10 $$%$$ of that for primary neutron reaction product $$^{54}$$Mn aound the surface of a cooling pipe in a fusion reactor. The effective cross sections were estimated by using (n,xp), (p,n) reaction cross sections, proton emission spectra, proton stopping power in the material. The estimated values were compared with experimental results.

Journal Articles

Radioactivity production around the surface of a cooling water pipe in a D-T fusion reactor by sequential charged particle reactions

Hori, Junichi; Maekawa, Fujio; Wada, Masayuki*; Ochiai, Kentaro; Yamauchi, Michinori*; Morimoto, Yuichi*; Terada, Yasuaki; Klix, A.; Nishitani, Takeo

Fusion Engineering and Design, 63-64, p.271 - 276, 2002/12

 Times Cited Count:2 Percentile:17.03(Nuclear Science & Technology)

In order to the waste management method and the safety design of future D-T fusion reactor, it is important to consider the radioactivity productions via not only primary neutron reactions but also sequential charged particle reactions (SCPR). Especially, on the surface of a coolant channel many recoiled protons are generated by the neutron irradiation with coolant water, so it is apprehensive that the undesirable radioactive nuclide production yields via SCPR are enhanced. In this work, the laminated sample pieces of fusion material foils (V, Fe, W, Ti, Pb, Cu) were made and attached on a polyethylene board to simulate water flowing inside a coolant channel. They were irradiated with D-T neutrons. The effective radioactivity cross section and the depth distribution of the radioactivity production yields due to SCPR were obtained for each material. On the other hand, the estimated values were compared with the experimental ones.

Journal Articles

Preliminary examination of the applicability of imaging plates to fast neutron radiography

Matsubayashi, Masahito; Hibiki, Takashi*; Mishima, Kaichiro*; Yoshii, Koji*; Okamoto, Koji*

Nuclear Instruments and Methods in Physics Research A, 463(1-2), p.324 - 330, 2001/05

 Times Cited Count:17 Percentile:73.21(Instruments & Instrumentation)

no abstracts in English

Journal Articles

Design of radial neutron spectrometer array for the International Thermonuclear Experimental Reactor

Nishitani, Takeo; Kasai, Satoshi; Iguchi, Tetsuo*; *; Ebisawa, Katsuyuki*; *

Review of Scientific Instruments, 68(1), p.565 - 568, 1997/01

 Times Cited Count:5 Percentile:46.16(Instruments & Instrumentation)

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:95.79(Instruments & Instrumentation)

no abstracts in English

JAEA Reports

Design of radial neutron spectrometer for ITER

Nishitani, Takeo; Iguchi, Tetsuo*; Ebisawa, Katsuyuki*; *; Kasai, Satoshi

JAERI-Tech 96-038, 29 Pages, 1996/09

JAERI-Tech-96-038.pdf:1.17MB

no abstracts in English

Journal Articles

Neutron spectrometers for ITER

Nishitani, Takeo; Iguchi, Tetsuo*; *; Kaneko, Junichi; Kasai, Satoshi; Matoba, Toru

Proc., Workshop on Diagnostics for Experimental Thermonuclear Fusion Reactors, 0, p.425 - 434, 1996/00

no abstracts in English

Journal Articles

Benchmark experiment on copper with D-T neutrons for verification of neutron transport and related nuclear data of JENDL-3.1

Konno, Chikara; Maekawa, Fujio; Oyama, Yukio; Ikeda, Yujiro; Maekawa, Hiroshi

Fusion Engineering and Design, 28, p.745 - 752, 1995/00

no abstracts in English

Journal Articles

A Review of shielding experiments for fusion reactor at FNS/JAERI

Maekawa, Hiroshi; Oyama, Yukio; Tanaka, Shunichi

Proc. of the Topical Meeting on New Horizons in Radiation Protection and Shielding, p.611 - 618, 1992/00

no abstracts in English

Journal Articles

Measurement and analysis of low energy neutron spectrum in a large cylindrical iron assembly bombarded by D-T neutrons

Konno, Chikara; Ikeda, Yujiro; Kosako, Kazuaki; Oyama, Yukio; Maekawa, Hiroshi; Nakamura, Tomoo; Bennett, E. F.*

Fusion Engineering and Design, 18, p.297 - 303, 1991/12

 Times Cited Count:16 Percentile:83.01(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Journal Articles

Comparison of measured and calculated neutron spectra in fast critical assembly

Journal of Nuclear Science and Technology, 17(6), p.471 - 473, 1980/00

 Times Cited Count:0 Percentile:0.29(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Journal Articles

Proton-recoil counter technique for measurement of fast neutron spectrum

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Journal of Nuclear Science and Technology, 16(5), p.329 - 343, 1979/05

 Times Cited Count:3

no abstracts in English

15 (Records 1-15 displayed on this page)
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