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Chae, H.*; Huang, E.-W.*; Jain, J.*; Lee, D.-H.*; Harjo, S.; Kawasaki, Takuro; Lee, S. Y.*
Metals and Materials International, 30(5), p.1321 - 1330, 2024/05
Komeda, Masao; Toh, Yosuke
Annals of Nuclear Energy, 135, p.106993_1 - 106993_6, 2020/01
Times Cited Count：2 Percentile：23.63(Nuclear Science & Technology)This paper presents a conceptual study of a novel active method using a neutron source. The main feature of this new method is the fast rotation of a neutron source in order to derive the fission neutron counts and applying the counts to detect the nuclear material. Irradiating neutrons to a container that involves nuclear material, the measurement data include both neutrons from the neutron source and fission neutrons. However, if the neutron source is rotated quite fast, the components of the irradiation neutrons and fission neutrons are separated. Since this novel method does not require an expensive D-T tube, this new system is expected to be affordable and easy to assemble.
Amaya, Masaki; Kakiuchi, Kazuo; Mihara, Takeshi
Proceedings of International Nuclear Fuel Cycle Conference / Light Water Reactor Fuel Performance Conference (Global/Top Fuel 2019) (USB Flash Drive), p.1048 - 1056, 2019/09
Tobita, Toru; Nishiyama, Yutaka; Onizawa, Kunio
JAEA-Data/Code 2018-013, 60 Pages, 2018/11
JAEA-Data-Code-2018-013.pdf:1.67MB
Mechanical properties of materials including fracture toughness are extremely important for evaluating the structural integrity of reactor pressure vessels (RPVs). In this report, the published data of mechanical properties of nuclear RPVs steels, including neutron irradiated materials, acquired by the Japan Atomic Energy Agency (JAEA), specifically tensile test data, Charpy impact test data, drop-weight test data, and fracture toughness test data, are summarized. There are five types of RPVs steels with different toughness levels equivalent to JIS SQV2A (ASTM A533B Class 1) containing impurities in the range corresponding to the early plant to the latest plant. In addition to the base material of RPVs, the mechanical property data of the two types of stainless overlay cladding materials used as the lining of the RPV are summarized as well. These mechanical property data are organized graphically for each material and listed in tabular form to facilitate easy utilization of data.
Rossi, F.; Rodriguez, D.; Takahashi, Tone; Seya, Michio; Koizumi, Mitsuo
Nihon Kaku Busshitsu Kanri Gakkai Dai-39-Kai Nenji Taikai Rombunshu (CD-ROM), 3 Pages, 2018/11
This paper (presentation) reports on the design study for seeking compactness of moderator (and reflector) structure for the Delayed Gamma-ray Spectroscopy Non Destructive Assay system to be applied for verification of fissile isotopic (Pu-239, Pu-241 and U-235) composition ratio in High Radioactive Nuclear Material sample such as dissolved solution of reprocessing facility. We first investigated advantages and disadvantages of using different compact neutron sources as DT and DD neutron generators. This led us to the conclusion of using DD sources to achieve a compact (and practical) NDA system. Based on MCNP simulations, with the use of a DD neutron generator, a preliminary optimization study was performed and will be shown here.
Seya, Michio; Hajima, Ryoichi*; Kureta, Masatoshi
Proceedings of INMM 58th Annual Meeting (Internet), 10 Pages, 2017/07
Large size freight cargo containers are the most vulnerable items from nuclear security points of view because of their large volume and weight of cargo inside for hiding heavily shielded objects. For strengthening nuclear security, secure detection of NMs in heavily shielded objects, and safe handling (dismantlement) of detected (suspicious) objects, are essential. These require secure detection of NMs, inspection of detailed interior structures of detected objects, rough characterization of NMs (for nuclear bomb or RDD etc.) and confirmation of existence of explosives etc. By using information obtained by these inspections, safe dismantlement of objects is possible. In this paper, we propose a combination of X-ray scanning system with NRF-based NDD system using monochromatic 
-ray beam for a secure detection and interior inspections. We also we propose active neutron NDA system using a DT source for interior inspection of NM part.
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：0.01(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 
m in thickness.The a particle and triton were produced by 
Be(n,
)
He, Be(n,2n)2 and Be(n,t)
Li reactions respectively. Measured total reaction rates from the counts of a particles and tritons were 2.7
10
and 610
/atom/neutron, respectively, which were consistent with the calculated values from the nuclear data JENDL-3.2.
studyMatsumura, Akira*; Zhang, T.*; Nakai, Kei*; Endo, Kiyoshi*; Kumada, Hiroaki; Yamamoto, Tetsuya*; Yoshida, Fumiyo*; Sakurai, Yoshinori*; Yamamoto, Kazuyoshi; Nose, Tadao*
Journal of Experimental and Clinical Cancer Research, 24(1), p.93 - 98, 2005/03
no abstracts in English
Koura, Hiroyuki; Tachibana, Takahiro*; Uno, Masahiro*; Yamada, Masami*
Progress of Theoretical Physics, 113(2), p.305 - 325, 2005/02
Times Cited Count：399 Percentile：99.17(Physics, Multidisciplinary)A nuclidic mass formula composed of a gross term, an even-odd term and a shell term is presented as a revised version of the mass formula constructed by the present authors and published in 2000. The gross term has almost the same functional form as in the previous formula, but the parameter values in it are somewhat different. The even-odd term is treated more carefully, and a considerable improvement is brought about. The shell term is exactly the same as the previous one; it was obtained using spherical single-particle potentials and by treating the deformed nucleus as a superposition of spherical nuclei. The new mass formula is applicable to nuclei with 
1 and 
1. The root-mean-square deviation from experimental masses is 0.658 MeV, which is less than that of the previous mass formula, 0.680 MeV.
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：10 Percentile：55.63(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.
-ray analysis using 
-standardizationMatsue, Hideaki; Yonezawa, Chushiro
Bunseki Kagaku, 53(7), p.749 - 751, 2004/07
Times Cited Count：0 Percentile：0.01(Chemistry, Analytical)Multi-element determination in reference materials of soils (JASC401, JASC411) and sediments (NMIJ CRM 7302-a, NMIJ CRM 7303-a), which were prepared at the Japan Society for Analytical Chemistry and the National Institute of Advanced Industrial Science and Technology of the National Metrology Institute of Japan, respectively, has been carried out by neutron-induced prompt -ray analysis (PGA) using standard addition and -standardization methods. Firstly, absolute Ti concentrations in the samples were determined accurately by the standard addition method. Secondly, relative multi-element concentrations were determined by the -standardization method. Finally, absolute multi-element concentrations were obtained by normalizing the relative multi-element concentrations with the absolute Ti concentration in the samples. The 15 elements such as H, B, Na, Si, S, Cl, K, Ca, Ti Cr, Mn, Fe, Cd, Sm and Gd were determined by the -PGA. Analytical results of these reference materials agreed with the certified or reference values within about 10%.
NCT trialZhang, T.*; Matsumura, Akira*; Yamamoto, Tetsuya*; Yoshida, Fumiyo*; Sakurai, Yoshinori*; Kumada, Hiroaki; Yamamoto, Kazuyoshi; Nose, Tadao*
Research and Development in Neutron Capture Therapy, p.819 - 824, 2002/09
From present study, the irradiation effect by using combination of Boron and Gd, showed various irradiation effects (additive effect, less than additive effect, non additive effect), which depend on Gd concentration. The additive effect will be occurred when using a combination of Gd and Boron with low concentration, however, adding Gd to high concentration will reduce additive effect resulting in less than additive to finally non-additive effect. This result indicate that achieving suitable concentrations of Gd and Boron together in tumors may increase the therapy effect, but achieving excess concentration of Gd with Boron together in tumor may cause negative therapeuitic effect.
Kugo, Teruhiko
Journal of Nuclear Science and Technology, 39(3), p.256 - 263, 2002/03
Times Cited Count：3 Percentile：23.39(Nuclear Science & Technology)Two vector computation algorithms; an odd-even sweep (OES) method and an independent sequential sweep (ISS) method, have been developed for the characteristics method to solve the neutron transport equation in a heterogeneous geometry. They realize long vector lengths without recursive operations for effective use of vector computers. Their efficiency has been investigated to a realistic fuel assembly calculation. For both methods, a vector computation is 15 times faster than a scalar computation. From a viewpoint of a comparison between the OES and ISS methods, the ISS method is superior to the OES method because the ISS method shows a faster convergence and saves a computer memory without reducing a computation speed.
Kugo, Teruhiko
JAERI-Research 2001-051, 39 Pages, 2001/11
JAERI-Research-2001-051.pdf:2.04MB
Fast computation of the characteristics method to solve the neutron transport equation in a heterogeneous geometry has been studied. Two vector computation algorithms; an odd-even sweep (OES) method and an independent sequential sweep (ISS) method have been developed and their efficiency to a typical fuel assembly calculation has been investigated. For both methods, a vector computation is 15 times faster than a scalar computation. From a viewpoint of comparison between the OES and ISS methods, the ISS method is superior to the OES method because the ISS method shows a faster convergence and saves a computer memory without reducing a computation speed. In the vector computation, a table-look-up method to reduce computation time of an exponential function saves only 20% of a whole computation time. Both the coarse mesh rebalance method and the Aitken acceleration method are effective as acceleration methods for the characteristics method, a combination of them saves 70-80% of outer iterations compared with a free iteration.
Nagase, Fumihisa; Sugano, Mitsuteru*; Ozawa, Masaaki*; Komatsu, Kazushi*; Furuta, Teruo*
JAERI-Research 2001-008, 61 Pages, 2001/03
JAERI-Research-2001-008.pdf:2.62MB
no abstracts in English
Kaneko, Yoshihiko*; Nagao, Yoshiharu; Shimakawa, Satoshi
Journal of Nuclear Science and Technology, 36(11), p.988 - 995, 1999/11
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Kaneko, Yoshihiko*; Nagao, Yoshiharu; Yamane, Tsuyoshi; Takeuchi, Mitsuo
JAERI-Conf 99-006, p.316 - 321, 1999/08
no abstracts in English
Konno, Chikara; Maekawa, Fujio; *; Kosako, Kazuaki*; Ikeda, Yujiro; Oyama, Yukio; Maekawa, Hiroshi
JAERI-Tech 94-019, 43 Pages, 1994/10
no abstracts in English
Ikezoe, Hiroshi; Shikazono, Naomoto; Nagame, Yuichiro; Sugiyama, Yasuharu; Tomita, Yoshiaki; Ideno, K.; *; B.J.Qi*; H.J.Kim*; Iwamoto, Akira; et al.
Physical Review C, 46(5), p.1922 - 1933, 1992/11
Times Cited Count：43 Percentile：89.14(Physics, Nuclear)no abstracts in English
B.Yu*; Chiba, Satoshi; Fukahori, Tokio
Journal of Nuclear Science and Technology, 29(7), p.677 - 689, 1992/07
no abstracts in English
