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Journal Articles

Study on neutron beam pulse width dependence in the nuclear fuel measurement by the neutron resonance transmission analysis

Kitatani, Fumito; Tsuchiya, Harufumi; Toh, Yosuke; Hori, Junichi*; Sano, Tadafumi*; Takahashi, Yoshiyuki*; Nakajima, Ken*

KURRI Progress Report 2017, P. 99, 2018/08

Journal Articles

Integral test of international reactor dosimetry and fusion file on graphite assembly with DT neutron at JAEA/FNS

Ota, Masayuki; Sato, Satoshi; Ochiai, Kentaro; Konno, Chikara

Fusion Engineering and Design, 98-99, p.1847 - 1850, 2015/10

 Times Cited Count:2 Percentile:69.57(Nuclear Science & Technology)

International Reactor Dosimetry and Fusion File release 1.0 (IRDFF 1.0), has been released from the International Atomic Energy Agency (IAEA) recently. In order to validate and test IRDFF 1.0, IAEA has initiated a new Co-ordinated Research Project (CRP). Under this CRP, we have performed an integral experiment on a graphite pseudo-cylindrical slab assembly with DT neutron source at JAEA/FNS. The graphite assembly of 31.4 cm in equivalent radius and 61 cm in thickness is placed at a distance of about 20 cm from the DT neutron source. A lot of foils for the dosimetry reactions in IRDFF1.0 are inserted into the small spaces between the graphite blocks along the center axis of the assembly. After DT neutron irradiation, reaction rates for the dosimetry reactions are measured by the foil activation technique. This experiment is analyzed by using Monte Carlo neutron transport code MCNP5-1.40 with recent nuclear data libraries of ENDF/B-VII.1, JEFF-3.2, and JENDL-4.0. The experimental assembly and DT neutron source are modeled precisely in the MCNP calculation. The reaction rates calculated with IRDFF 1.0 as the response functions for the dosimetry reactions are compared with the experimental values. Also the calculations with JENDL Dosimetry File 99 (JENDL/D-99) are performed for comparison. The results calculated with IRDFF 1.0 show good agreement with the experimental results.

Journal Articles

New approach to measure double-differential charged-particle emission cross sections of several materials for a fusion reactor

Kondo, Keitaro; Takagi, Satoshi*; Murata, Isao*; Miyamaru, Hiroyuki*; Takahashi, Akito*; Kubota, Naoyoshi; Ochiai, Kentaro; Nishitani, Takeo

Fusion Engineering and Design, 81(8-14), p.1527 - 1533, 2006/02

 Times Cited Count:12 Percentile:29.89(Nuclear Science & Technology)

In a fusion reactor development, double-differential charged-particle emission cross sections(DDXc) are necessary to estimate nuclear heating and material damages of candidate materials irradiated with neutrons. Especially in light nuclei such as Be, Li, and C, nuclear reactions are complicated and difficult to estimate energy spectra of emitted particles based only on theoretical calculations Therefore development of a new technique for precise measurements of DDXc is quite important. Recently we successfully developed a new spectrometer for measurement of DDXc using a pencil-beam DT neutron source of FNS in JAERI. In the present study we carried out measurements of DDXc of $$^{9}$$Be, $$^{12}$$C, $$^{19}$$F, and $$^{27}$$Al using the spectrometer. The present technique was valid from the result of measurement for the $$^{27}$$Al(n,x$$alpha$$) reactions. Slight differences appeared between measured data and evaluation or previous experimental values for $$^{9}$$Be(n,x$$alpha$$) reactions at backward scattering angle and in lower energy region.

Journal Articles

Measurement of energetic charged particles produced in fusion materials with 14 MeV neutron irradiation

Ochiai, Kentaro; Kondo, Keitaro; Murata, Isao*; Miyamaru, Hiroyuki*; Kubota, Naoyoshi; Takahashi, Akito*; Nishitani, Takeo

Fusion Engineering and Design, 75-79, p.859 - 863, 2005/11

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

The Fusion Neutronics Source (FNS) of JAERI currently carries out the measurements of energetic charged particles emitted from fusion materials irradiated with a well-collimated 14 MeV neutron beam. At the beginning, the double differential cross section beryllium was measured. We have measured proton, triton and a particle emitted from a beryllium sample of 100 $$mu$$m in thickness.The a particle and triton were produced by $$^{9}$$Be(n,$$alpha$$)$$^{6}$$He, $$^{9}$$Be(n,2n)2$$alpha$$ and $$^{9}$$Be(n,t)$$^{7}$$Li reactions respectively. Measured total reaction rates from the counts of a particles and tritons were 2.7$$times$$10$$^{-24}$$ and 6$$times$$10$$^{-27}$$/atom/neutron, respectively, which were consistent with the calculated values from the nuclear data JENDL-3.2.

Journal Articles

Neutronic performance of rectangular and cylindrical coupled hydrogen moderators in wide-angle beam extraction of low-energy neutrons

Kai, Tetsuya; Harada, Masahide; Teshigawara, Makoto; Watanabe, Noboru; Kiyanagi, Yoshiaki*; Ikeda, Yujiro

Nuclear Instruments and Methods in Physics Research A, 550(1-2), p.329 - 342, 2005/09

 Times Cited Count:12 Percentile:31.39(Instruments & Instrumentation)

Neutronic study was performed on coupled hydrogen moderators to maximize time-integrated and pulse-peak intensities of slow neutrons when a large number of beams was required. The total increased with the number of beams, although the average decreased due to a reflector-missing by the beam extraction holes in the reflector. At a large beam extraction angle (25 degree), the spatial distribution of the vector-flux of neutrons was undesirable for a rectangular shape moderator. As an alternative we proposed a cylindrical shape one, resulting in a much improved spatial distribution. In addition, neutronic performance was calculated as a function of the diameter, indicating the optimal diameter was about 140 mm. The cylindrical one gave higher pulse-peak intensities with narrower pulse widths without penalty in time-integrated intensities and pulse decay characteristics, providing a more uniform angle-dependence. Some explanations are given for the difference in the pulse characteristics between the two. We decided to adopt the cylindrical one for the Japanese spallation neutron source.

Journal Articles

Synthesis and ${it in vivo}$ evaluation of BPA-Gd-DTPA complex as an MRI contrast agent and as a carrier for neutron capture therapy

Takahashi, Kazunori*; Nakamura, Hiroyuki*; Furumoto, Shozo*; Yamamoto, Kazuyoshi; Matsumura, Akira*; Fukuda, Hiroshi*; Yamamoto, Yoshinori*

Proceedings of 11th World Congress on Neutron Capture Therapy (ISNCT-11) (CD-ROM), 1 Pages, 2004/10

We synthesized a BPA-Gd-DTPA compound, as a carrier for neutron capture therapy to be used for MRI contrast media. Pinanediol was used as the protective group for B(OH)2 group of BPA, and the BPA unit was connected to the DTPA framework through an amide bond. The biodistribution studies were performed after injection of the compound into AH109A hepatoma bearing Donryu rats. The concentrations of Gd and boron were measured by prompt g-ray analyses. The tumor uptakes (% ID/g) were 1% and 0.3% at 20 min and 60 min after injection, respectively and were higher than that of carborane-Gd-DTPA, which we previously reported. However, liver and kidney uptake was very high and tumor/blood ratio was very low (0.38) compared to that of BPA itself (ca. 3.0). Alfa autoradiogram of a tumor bearing rat showed higher concentration of boron in the tumor compared to surrounding muscle and very high in the intestine. Although tumor selectivity of the compound was higher than that of carborane-Gd-DTPA, further studies of the synthesis and in vivo evaluation of better binary compounds are continuing.

Journal Articles

Radioactivity of the vanadium-alloy induced by D-T neutron irradiation

Sato, Satoshi; Tanaka, Teruya*; Hori, Junichi; Ochiai, Kentaro; Nishitani, Takeo; Muroga, Takeo*

Journal of Nuclear Materials, 329-333(Part2), p.1648 - 1652, 2004/08

 Times Cited Count:1 Percentile:88.58(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Non-destructive analysis of impurities in beryllium, affecting evaluation of the tritium breeding ratio

Verzilov, Y. M.; Ochiai, Kentaro; Klix, A.; Sato, Satoshi; Wada, Masayuki*; Yamauchi, Michinori*; Nishitani, Takeo

Journal of Nuclear Materials, 329-333(Part2), p.1337 - 1341, 2004/08

 Times Cited Count:3 Percentile:73.23(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Irradiation and penetration tests of boron-doped low activation concrete using 2.45 MeV and 14 MeV neutron sources

Morioka, Atsuhiko; Sato, Satoshi; Kinno, Masaharu*; Sakasai, Akira; Hori, Junichi*; Ochiai, Kentaro; Yamauchi, Michinori*; Nishitani, Takeo; Kaminaga, Atsushi; Masaki, Kei; et al.

Journal of Nuclear Materials, 329-333(2), p.1619 - 1623, 2004/08

 Times Cited Count:6 Percentile:54.68(Materials Science, Multidisciplinary)

The neutron penetration and the activation characteristics of the boron-doped low activation concrete were investigated for irradiation of 2.45 and 14 MeV neutrons. The shielding property of the 2 wt% boron-doped low activation concrete is superior to that of the 1 wt% boron for the thermal neutron, on the contrary to the no clear difference for the fast neutron. The total activity detected in the boron-doped low activation concrete was about one hundredth of that in the geostandard sample at more than 30 days cooling time. The total activity of the boron-doped concrete by major nuclei does not depend on the boron density for the 14 MeV neutron irradiation.

Journal Articles

Experimental study on induced radioactivity in boron-doped low activation concrete for DT fusion reactors

Sato, Satoshi; Morioka, Atsuhiko; Kinno, Masaharu*; Ochiai, Kentaro; Hori, Junichi; Nishitani, Takeo

Journal of Nuclear Science and Technology, 41(Suppl.4), p.66 - 69, 2004/03

no abstracts in English

Journal Articles

J-PARC construction and its linac commissioning

Yamazaki, Yoshishige

Proceedings of 9th European Particle Accelerator Conference (EPAC 2004), p.1351 - 1353, 2004/00

The J-PARC (Japan Proton Accelerator Research Complex) is under construction in JAERI Tokai site. The beam commissioning will start there by the end of 2006. Prior to this, the front end of the linac was beam-commissioned in 2003 at KEK. The negative hydrogen beam with a peak current of 30 mA was accelerated up to 20 MeV by the first tank of the three DTL's following the 3-MeV RFQ linac. The 324-MHz DTL contains the electro quadrupole magnets with water-cooling channels specially fabricated by means of electroforming and wire-cutting technologies. The construction status of the J-PARC accelerator is also presented.

Journal Articles

Measurement of neutron energy spectrum below 10keV in an iron shield bombarded by deuterium-tritium neutrons and benchmark test of evaluated nuclear data from 14 MeV to 1 eV

Maekawa, Fujio; Oyama, Yukio

Nuclear Science and Engineering, 125(2), p.205 - 217, 1997/02

 Times Cited Count:3 Percentile:67.37(Nuclear Science & Technology)

no abstracts in English

Journal Articles

JAERI/USDOE collaborative experiments on fusion blanket neutronics

Oyama, Yukio

NCC Nyusu, 0(18), p.17 - 23, 1994/00

no abstracts in English

Journal Articles

Annular blanket experiment using a line DT neutron source; Phase IIIA of the JAERI/USDOE collaborative program on fusion neutronics

Oyama, Yukio; Konno, Chikara; Ikeda, Yujiro; Maekawa, Hiroshi; Kosako, Kazuaki*; Nakamura, Tomoo; A.Kumar*; M.Youssef*; M.Abdou*; E.Bennett*

Fusion Technology, 19(3), p.1879 - 1884, 1991/05

no abstracts in English

JAEA Reports

Experimental results of angular neutron flux spectra leaking from slabs of fusion reactor candidate materials, I

Oyama, Yukio; ; Maekawa, Hiroshi

JAERI-M 90-092, 124 Pages, 1990/06

JAERI-M-90-092.pdf:4.94MB

no abstracts in English

Journal Articles

Measurement and analysis of an angular neutron flux on a beryllium slab irradiated with deuterium-tritium neutrons

;

Nuclear Science and Engineering, 97, p.220 - 234, 1987/00

 Times Cited Count:23 Percentile:11.11(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Spectral measurement of angular neutron flux on the restricted surface of slab assemblies by the time-of-flight method

;

Nuclear Instruments and Methods in Physics Research A, 245, p.173 - 181, 1986/00

 Times Cited Count:7 Percentile:29.16

no abstracts in English

Journal Articles

Neutron field characteristics in concrete cavity having a D-T neutron source

; ; ; Nakagawa, Masayuki;

Transactions of the American Nuclear Society, 52, p.112 - 113, 1986/00

no abstracts in English

JAEA Reports

Journal Articles

Experimental study on neutron streaming through steel-walled annular ducts in reactor shields

*;

Nuclear Science and Engineering, 83, p.333 - 349, 1983/00

 Times Cited Count:4 Percentile:47.68(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Slow neutron resonances in terbium-159

;

Journal of Nuclear Science and Technology, 16(10), p.701 - 710, 1979/10

 Times Cited Count:1

no abstracts in English

21 (Records 1-20 displayed on this page)