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Journal Articles

KeV-neutron capture cross-section measurement of $$^{197}$$Au with a Cr-filtered neutron beam at the ANNRI beamline of MLF/J-PARC

Rovira Leveroni, G.; Kimura, Atsushi; Nakamura, Shoji; Endo, Shunsuke; Iwamoto, Osamu; Iwamoto, Nobuyuki; Katabuchi, Tatsuya*; Kodama, Yu*; Nakano, Hideto*; Sato, Yaoki*; et al.

Journal of Nuclear Science and Technology, 59(5), p.647 - 655, 2022/05

Journal Articles

Measurements of the neutron capture cross section of $$^{243}$$Am around 23.5 keV

Kodama, Yu*; Katabuchi, Tatsuya*; Rovira Leveroni, G.; Kimura, Atsushi; Nakamura, Shoji; Endo, Shunsuke; Iwamoto, Nobuyuki; Iwamoto, Osamu; Hori, Junichi*; Shibahara, Yuji*; et al.

Journal of Nuclear Science and Technology, 58(11), p.1159 - 1164, 2021/11

Journal Articles

Micro-PIXE analysis study of ferrite products synthesized from simulated radioactive liquid waste containing chemical hazardous elements

Abe, Tomohisa; Shimazaki, Takejiro; Osugi, Takeshi; Nakazawa, Osamu; Yamada, Naoto*; Yuri, Yosuke*; Sato, Takahiro*

QST-M-16; QST Takasaki Annual Report 2017, P. 140, 2019/03

no abstracts in English

Journal Articles

Investigation of hydrogen gas generation by radiolysis for cement-solidified products of used adsorbents for water decontamination

Sato, Junya; Kikuchi, Hiroshi*; Kato, Jun; Sakakibara, Tetsuro; Matsushima, Ryotatsu; Sato, Fuminori; Kojima, Junji; Nakazawa, Osamu

QST-M-8; QST Takasaki Annual Report 2016, P. 62, 2018/03

no abstracts in English

Journal Articles

The Hydrogen gas generation by electron-beam irradiation from ALPS adsorbents solidified by several inorganic materials

Sato, Junya; Suzuki, Shinji*; Kato, Jun; Sakakibara, Tetsuro; Meguro, Yoshihiro; Nakazawa, Osamu

QST-M-2; QST Takasaki Annual Report 2015, P. 87, 2017/03

no abstracts in English

Journal Articles

The Hydrogen gas generation by gamma-ray irradiation from ALPS adsorbents solidified by several inorganic materials

Sato, Junya; Suzuki, Shinji*; Kato, Jun; Sakakibara, Tetsuro; Meguro, Yoshihiro; Nakazawa, Osamu

QST-M-2; QST Takasaki Annual Report 2015, P. 88, 2017/03

no abstracts in English

Journal Articles

Element distribution measurement in incineration ash using micro-PIXE analysis

Abe, Tomohisa; Shimazaki, Takejiro; Nakayama, Takuya; Osone, Osamu; Osugi, Takeshi; Nakazawa, Osamu; Yuri, Yosuke*; Yamada, Naoto*; Sato, Takahiro*

QST-M-2; QST Takasaki Annual Report 2015, P. 83, 2017/03

no abstracts in English

Journal Articles

Approaches of selection of adequate conditioning methods for various radioactive wastes in Fukushima Daiichi NPS

Meguro, Yoshihiro; Nakagawa, Akinori; Kato, Jun; Sato, Junya; Nakazawa, Osamu; Ashida, Takashi

Proceedings of International Conference on the Safety of Radioactive Waste Management (Internet), p.139_1 - 139_4, 2016/11

A variety of radioactive wastes have been generated in decommissioning of Fukushima Daiichi Nuclear Power Station. It is necessary to evaluate feasibility of conditioning methods to these wastes, because the majority of such wastes have not been solidified in Japan. The authors investigated an approach for screening of conditioning methods for the Fukushima wastes on the basis of the findings of the existing methods and results of fundamental solidification tests using synthetic Fukushima wastes. Here five solidification methods were selected, and also 13 wastes with different chemical composition are solidified, and characteristics of the solidified form are studied. A screening flow was proposed, and evaluation criteria on each step in the flow was set up. In this presentation a trial result was opened for a waste and improvements of the screening flow found in the trial evaluation was described.

Journal Articles

Overview of JENDL-4.0/HE and benchmark calculations

Kunieda, Satoshi; Iwamoto, Osamu; Iwamoto, Nobuyuki; Minato, Futoshi; Okamoto, Tsutomu; Sato, Tatsuhiko; Nakashima, Hiroshi; Iwamoto, Yosuke; Iwamoto, Hiroki; Kitatani, Fumito; et al.

JAEA-Conf 2016-004, p.41 - 46, 2016/09

Neutron- and proton-induced cross-section data are required in a wide energy range beyond 20 MeV, for the design of accelerator applications. New evaluations are performed with recent knowledge in the optical and pre-equilibrium model calculations. We also evaluated cross-sections for p+$$^{6,7}$$Li and p+$$^{9}$$Be which have been highly requested from a medical field. The present high-energy nuclear data library, JENDL-4.0/HE, includes evaluated cross-sections for incident neutrons and protons up to 200 MeV (for about 130 nuclei). We overview substantial features of the library, i.e., (1) systematic evaluation with CCONE code, (2) challenges for evaluations of light nuclei and (3) inheritance of JENDL-4.0 and JENDL/HE-2007. In this talk, we also focus on the results of benchmark calculation for neutronics to show performance of the present library.

JAEA Reports

Enhancement of control rod drive mechanism seating position detector for JRR-3

Ouchi, Satoshi; Kurumada, Osamu; Kamiishi, Eigo; Sato, Masayuki; Ikekame, Yoshinori; Wada, Shigeru

JAEA-Technology 2016-015, 42 Pages, 2016/06

JAEA-Technology-2016-015.pdf:3.53MB

The purpose of the control rod drive mechanism seating position detector for JRR-3 is one of a method for confirming the shutdown condition of the reactor. The detector has been utilizing more than 25 years with maintenance regularly. However, it is occurred some trouble recently. Moreover, the detector has already been end of manufacture, and even in the successor detector, it unsuitable for the control rod drive mechanism of JRR-3 was confirmed. Therefore, it was necessary to select the adequate detector to the control rod drive mechanism of JRR-3. Accordingly, we built a test device with the aim of verify several detectors for integrity and function. At the time of the test for performance confirmation, it was occurred unexpected problems. Nevertheless, we devise improvement of the problems and took measures. Thus we were able to collect adequate detector for JRR-3 and replace to enhanced detector. This paper reports the Enhanced of Control rod drive mechanism seat position detector.

JAEA Reports

Replacement of power supply for reactor control rod magnet of JRR-3

Kurumada, Osamu; Ikekame, Yoshinori; Ouchi, Satoshi; Sato, Masayuki; Kamiishi, Eigo; Wada, Shigeru

JAEA-Technology 2015-056, 35 Pages, 2016/03

JAEA-Technology-2015-056.pdf:29.49MB

The power supply for reactor control rod magnet of JRR-3 has been utilized for generating electromagnetic power of control rod coil and that was using more than 25 years. The power supply was required for provide to stabilize DC current. Therefore, we adopted series regulator method. Although, the power supply generate a high heat. Then, we decided to create switching regulator method in order to improve the aging and heat generation of the series regulator method. This paper reports the replacement of switching regulator method.

Journal Articles

Measurements and evaluations of air dose rates around the Fukushima NPP site, 6; Status and issues on evaluation of individual doses due to external exposures

Saito, Kimiaki; Kurihara, Osamu*; Matsuda, Norihiro; Takahara, Shogo; Sato, Tetsuro*

Radioisotopes, 65(2), p.93 - 112, 2016/02

Late information is introduced on dose evaluation due to external exposures which employ an important role in the exposures due to the Fukushima accident. First, merits and demerits of the currently used two methods, that is the estimation based air dose rates and the measurements using personal dosimeters, are discussed indicating some basic data after a fundamental concept of external dose evaluation is provided. Next, main activities are summarized on external dose measurements and evaluations after the accident. Finally, a new trial on dose evaluation in introduced.

Journal Articles

Progress and prospects of calculation methods for radiation shielding

Hirayama, Hideo*; Nakashima, Hiroshi; Morishima, Makoto*; Uematsu, Mikio*; Sato, Osamu*

Journal of Nuclear Science and Technology, 52(11), p.1339 - 1361, 2015/11

AA2014-0681.pdf:1.15MB

 Times Cited Count:3 Percentile:11.46(Nuclear Science & Technology)

Progress in calculation methods for radiation shielding are reviewed based on basis of the activities of research committees related to radiation shielding fields established in the Atomic Energy Society of Japan. A technological roadmap for the field of radiation shielding, progress and prospects for specific shielding calculation methods such as the Monte Carlo, discrete ordinate Sn transport, and simplified methods, and shielding experiments used to validate calculation methods are presented in this paper.

Journal Articles

PHITS simulation of quasi-monoenergetic neutron sources from $$^7$$Li($$p$$,$$n$$) reactions

Hashimoto, Shintaro; Iwamoto, Osamu; Iwamoto, Yosuke; Sato, Tatsuhiko; Niita, Koji*

Energy Procedia, 71, p.191 - 196, 2015/05

 Times Cited Count:2 Percentile:88.64

Accelerator-based neutron sources using proton- and deuteron-induced reactions have been utilized for scientific and medical applications, such as irradiation testing of fusion reactor materials at IFMIF and BNCT. Quasi-monoenergetic neutron beams using $$^7$$Li($$p$$,$$n$$)$$^7$$Be are of special importance for calibrating a detector and measuring cross sections for neutron induced reactions. PHITS can deal with the transport of incident protons as well as secondary neutrons using various physics models, and it can estimate particle fluxes in the beam line and energy deposition in shielding materials. Therefore, PHITS is a useful code for neutron source design in accelerator facilities. However, nuclear reaction models implemented in PHITS, such as INC, were not enough to reproduce the peak structure in neutron spectra of experimental data, since these models do not consider the transition process of $$^7$$Li($$p$$,$$n$$)$$^7$$Be. We have developed a new option that adds peaks obtained by the DWBA method, which gives cross sections of the transition on the basis of quantum mechanics, to results calculated by the INC model. We had applied this option to estimate neutron spectra in the reactions at incident energies below 50 MeV. Results of the INC model using the option had been in good agreement with experimental data. In this study, we extended the applicable incident energy range up to 400 MeV for the $$^7$$Li($$p$$,$$xn$$) reactions. We will show the comparison between the calculated result and experimental data, and discuss the validity of the option for the reactions.

Journal Articles

Fabrication of microstructures embedded in SC-CVD diamond with a focused proton microbeam

Kada, Wataru*; Kambayashi, Yuya*; Miura, Kenta*; Saruya, Ryota*; Kubota, Atsushi*; Sato, Takahiro; Koka, Masashi; Kamiya, Tomihiro; Hanaizumi, Osamu*

Key Engineering Materials, 643, p.15 - 19, 2015/05

Journal Articles

Development of embedded Mach-Zehnder optical waveguide structures in polydimethylsiloxane thin films by proton beam writing

Kada, Wataru*; Miura, Kenta*; Kato, Hijiri*; Saruya, Ryota*; Kubota, Atsushi*; Sato, Takahiro; Koka, Masashi; Ishii, Yasuyuki; Kamiya, Tomihiro; Nishikawa, Hiroyuki*; et al.

Nuclear Instruments and Methods in Physics Research B, 348, p.218 - 222, 2015/04

 Times Cited Count:6 Percentile:54.79(Instruments & Instrumentation)

Journal Articles

Replacement of power supply for reactor control rod magnet

Kurumada, Osamu; Ouchi, Satoshi; Sato, Masayuki; Kamiishi, Eigo; Ikekame, Yoshinori

UTNL-R-0489, p.8_1 - 8_8, 2015/03

no abstracts in English

Journal Articles

First measurement of the radionuclide purity of the therapeutic isotope $$^{67}$$Cu produced by $$^{68}$$Z($$n$$,$$x$$) reaction using $$^{rm nat}$$C($$d$$,$$n$$) neutrons

Sato, Nozomi; Tsukada, Kazuaki; Watanabe, Satoshi; Ishioka, Noriko; Kawabata, Masako; Saeki, Hideya; Nagai, Yasuki; Kin, Tadahiro*; Minato, Futoshi; Iwamoto, Nobuyuki; et al.

Journal of the Physical Society of Japan, 83(7), p.073201_1 - 073201_4, 2014/07

 Times Cited Count:12 Percentile:66.54(Physics, Multidisciplinary)

We have for the first time demonstrated that the therapeutic nuclide of $$^{67}$$Cu produced by $$^{68}$$Zn($$n$$,$$x$$)$$^{67}$$Cu has highest radionuclide purity compared to previous ones. We measured a $$gamma$$-ray spectrum of the reaction product produced by bombarding an enriched $$^{68}$$Zn sample with neutrons with a HPGe detector. The neutrons were obtained by $$^{rm nat}$$C($$d$$,$$n$$) using 41 MeV deuterons provided from Takasaki Ion Accelerators for Advanced Radiation Application of Japan Atomic Energy Agency. Relative production yields of impurity radionuclides such as $$^{65}$$Zn to $$^{67}$$Cu are extremely low, which allow us to chemically separate $$^{67}$$Cu from an irradiated $$^{68}$$Zn sample with a few steps and to reuse high cost an enriched $$^{68}$$Zn sample. The present result strongly suggest that the $$^{68}$$Zn($$n$$,$$x$$)$$^{67}$$Cu reaction is the most promising route to produce high quality $$^{67}$$Cu and could solve a longstanding problem of establishing an appropriate production method of $$^{67}$$Cu.

Journal Articles

Expansion control for cementation of incinerated ash

Nakayama, Takuya; Suzuki, Shinji; Hanada, Keiji; Tomioka, Osamu; Sato, Junya; Irisawa, Keita; Kato, Jun; Kawato, Yoshimi; Meguro, Yoshihiro

Proceedings of 2nd International Symposium on Cement-based Materials for Nuclear Wastes (NUWCEM 2014) (CD-ROM), 12 Pages, 2014/06

Journal Articles

New approach for nuclear reaction model in the combination of intra-nuclear cascade and DWBA

Hashimoto, Shintaro; Iwamoto, Osamu; Iwamoto, Yosuke; Sato, Tatsuhiko; Niita, Koji*

Nuclear Data Sheets, 118, p.258 - 261, 2014/05

 Times Cited Count:4 Percentile:36.66(Physics, Nuclear)

Particle transport simulation codes based on the Monte Carlo technique are utilized to predict interaction of radiations with materials. The codes describe the transport of all particles, e.g. photons, electrons, nucleons, and heavy ions by various models for physical processes and nuclear reaction. In particular, nuclear reaction processes are essential parts for the accurate prediction. Recently, accelerator-based neutron sources using proton or deuteron beams with energies from 10 to 100 MeV come to be utilized for scientific and medical applications. For neutron source design, accurate description of neutron yields created by nuclear reactions is required in the simulation. However, the Intra-Nuclear Cascade type models used in most of the simulation codes are not enough to reproduce experimental data because of neglecting quantum mechanical effects. In this study, we combined the cascade type models and an event generator using the DWBA (Distorted Wave Born Approximation) calculation, which is a theoretical model based on quantum mechanics. We verified that the calculated results with the combination model can reproduce experimental data of neutron spectra in deuteron-induced reactions. We will also present the validity of the combination model for proton-induced reactions.

230 (Records 1-20 displayed on this page)