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Journal Articles

Microanalysis of silica-based adsorbent for effective recovery of radioactive elements

Sano, Yuichi; Watanabe, So; Matsuura, Haruaki*; Nagoshi, Kohei*; Arai, Tsuyoshi*

Journal of Nuclear Science and Technology, 54(10), p.1058 - 1064, 2017/10

 Times Cited Count:3 Percentile:53.18(Nuclear Science & Technology)

For effective recovery of radioactive elements by adsorbents using polymer-immobilized silica (SiO$$_{2}$$-P) supports, the microstructure of SiO$$_{2}$$-P particles impregnated with CMPO as extractants and their change with the crosslinking degree of polymer (CDP) were investigated using STXM and EXAFS analyses; further, their relation with adsorption/elution behavior was discussed. The adsorption/elution tests using adsorbents with a different CDP demonstrated that a higher CDP inhibited the elution of adsorbed metal ions from the adsorbent. The results of STXM and EXAFS analyses suggested that adsorption by CMPO proceeds through the entire area in the adsorbent and the local structure around adsorbed metal ions is similar irrespective of the CDP. Conversely, STXM analyses implied the capture of eluents such as H$$_{2}$$O by polymers with high CDP, which suppresses the prompt elution of adsorbed metal ions from the adsorbent.

Journal Articles

Reliability estimation of neutron resonance thermometry using tantalum and tungsten

Kai, Tetsuya; Hiroi, Kosuke; Su, Y.; Shinohara, Takenao; Parker, J. D.*; Matsumoto, Yoshihiro*; Hayashida, Hirotoshi*; Segawa, Mariko; Nakatani, Takeshi; Oikawa, Kenichi; et al.

Physics Procedia, 88, p.306 - 313, 2017/06

 Times Cited Count:3 Percentile:8.36

JAEA Reports

MVP/GMVP version 3; General purpose Monte Carlo codes for neutron and photon transport calculations based on continuous energy and multigroup methods

Nagaya, Yasunobu; Okumura, Keisuke; Sakurai, Takeshi; Mori, Takamasa

JAEA-Data/Code 2016-018, 421 Pages, 2017/03


In order to realize fast and accurate Monte Carlo simulation of neutron and photon transport problems, two Monte Carlo codes MVP (continuous-energy method) and GMVP (multigroup method) have been developed at Japan Atomic Energy Agency. The codes have adopted a vectorized algorithm and have been developed for vector-type supercomputers. They also support parallel processing with a standard parallelization library MPI and thus a speed-up of Monte Carlo calculations can be achieved on general computing platforms. The first and second versions of the codes were released in 1994 and 2005, respectively. They have been extensively improved and new capabilities have been implemented. The major improvements and new capabilities are as follows: (1) perturbation calculation for effective multiplication factor, (2) exact resonant elastic scattering model, (3) calculation of reactor kinetics parameters, (4) photo-nuclear model, (5) simulation of delayed neutrons, (6) generation of group constants, etc. This report describes the physical model, geometry description method used in the codes, new capabilities and input instructions.

Journal Articles

Spectrum-dose conversion operator of NaI(Tl) and CsI(Tl) scintillation detectors for air dose rate measurement in contaminated environments

Tsuda, Shuichi; Saito, Kimiaki

Journal of Environmental Radioactivity, 166(Part 3), p.419 - 426, 2017/01

 Times Cited Count:15 Percentile:28.53(Environmental Sciences)

Air dose rate monitoring in the environment has been performed since the Fukushima Dai-ichi Nuclear Power Plant accident happened. In the measurement, NaI(Tl) and CsI(Tl) scintillation detectors are used, which are usually used in nuclear power plants and calibrated in a uniform irradiation condition in a radiation calibration field. In general, however, the detector responses are dependent on incident direction and in reality, the incident direction of the photons is not uniform in the environment. In this study, to evaluate the dependence of dose on the photon incident direction, the spectrum - dose conversion operator (G(E) function) for air kerma in a semi-infinite radiation field were obtained using the PHITS code for commonly used NaI(Tl) and CsI(Tl) scintillation detectors. The results indicate that the commonly used scintillation detectors overestimate the doses by a maximum of 40% for mono-energetic photons but under the real environment, one could obtain the dose in the semi-infinite radiation field within 20%.

Journal Articles

Measurement of the $$^{77}$$Se($$gamma$$, n) cross section and uncertainty evaluation of the $$^{79}$$Se(n, $$gamma$$) cross section

Kitatani, Fumito; Harada, Hideo; Goko, Shinji*; Iwamoto, Nobuyuki; Utsunomiya, Hiroaki*; Akimune, Hidetoshi*; Toyokawa, Hiroyuki*; Yamada, Kawakatsu*; Igashira, Masayuki*

Journal of Nuclear Science and Technology, 53(4), p.475 - 485, 2016/04

 Times Cited Count:2 Percentile:71.23(Nuclear Science & Technology)

Journal Articles

Activation and control of visible single defects in 4H-, 6H-, and 3C-SiC by oxidation

Lohrmann, A.*; Castelletto, S.*; Klein, J. R.*; Oshima, Takeshi; Bosi, M.*; Negri, M.*; Lau, D. W. M.*; Gibson, B. C.*; Prawer, S.*; McCallum, J. C.*; et al.

Applied Physics Letters, 108(2), p.021107_1 - 021107_4, 2016/01

 Times Cited Count:24 Percentile:17.17(Physics, Applied)

Journal Articles

Defect engineering in silicon carbide; Single photon sources, quantum sensors and RF emitters

Kraus, H.; Simin, D.*; Fuchs, F.*; Onoda, Shinobu; Makino, Takahiro; Dyakonov, V.*; Oshima, Takeshi

Proceedings of 11th International Workshop on Radiation Effects on Semiconductor Devices for Space Applications (RASEDA-11) (Internet), p.176 - 179, 2015/11

Journal Articles

Room temperature quantum emission from cubic silicon carbide nanoparticles

Castelletto, S.*; Johnson, B. C.*; Zachreson, C.*; Beke, D.*; Balogh, I.*; Oshima, Takeshi; Aharonovich, I.*; Gali, A.*

ACS Nano, 8(8), p.7938 - 7947, 2014/08

Journal Articles

Study of radiation-induced primary process by ion pulse radiolysis

Yoshida, Yoichi*; Yang, J.*; Kondo, Takafumi*; Seki, Shuhei*; Kozawa, Takahiro*; Tagawa, Seiichi*; Shibata, Hiromi*; Taguchi, Mitsumasa; Kojima, Takuji; Namba, Hideki

JAEA-Review 2005-001, TIARA Annual Report 2004, p.183 - 185, 2006/01

A heavy-ion-pulse radiolysis technology was developed using a single-photon-counting system. In the system, the ion beam was injected a thin scintillator before irradiating the sample. The light emitted from the scintillator by the ion irradiation was used as analyzing source to detect the absorption of primary species in water. Measurement of time-dependent absorption of hydrated electrons in water was achieved using the system, which demonstrates the usefulness of this technique.

Journal Articles

Comparison of synchrotron radiation calculations between analytical codes(STAC8,PHOTON) and Monte Carlo codes (FLUKA,EGS4)

Liu, J. C.*; Fasso, A.*; Prinz, A.*; Rokni, S.*; Asano, Yoshihiro

Radiation Protection Dosimetry, 116(1-4), p.658 - 661, 2005/12

 Times Cited Count:6 Percentile:56.65(Environmental Sciences)

no abstracts in English

Journal Articles

Calculations for the availability of photoneutron using synchrotron radiation

Asano, Yoshihiro; Kawashima, Yoshitaka*

Radiation Protection Dosimetry, 115(1-4), p.176 - 180, 2005/12

 Times Cited Count:0 Percentile:100(Environmental Sciences)

no abstracts in English

Journal Articles

Development of lung and soft tissue substitutes for photons

Kinase, Sakae; Kimura, Masaya*; Noguchi, Hiroshi; Yokoyama, Sumi

Radiation Protection Dosimetry, 115(1-4), p.284 - 288, 2005/12

 Times Cited Count:10 Percentile:40.01(Environmental Sciences)

We have developed polyurethane-based tissue substitutes simulating lung, soft tissue, muscle, muscle-adipose mixture tissue, cartilage, brain, larynx, trachea, thyroid, kidney, liver and skin. The formulation of the tissue substitutes for photons was based on the basic data method together with an equation for calculating the optimum relative mass of corrective additives. The tissue substitutes were formulated to be phantom materials in the photon energy range of at least 10 keV-10 MeV. In particular, they were designed to match the tissues with linear attenuation coefficients for low photon energy (13.6, 17.2 and 20.2 keV from $$^{239}$$Pu) and to have the same mass densities as the tissues. The tissue substitutes developed in the present study were examined for the photon transmissions using 16.6 keV KX-rays from $$^{93}$$Nb$$^{m}$$. The experimental transmission curves of the substitutes were found to be in good agreement with those derived from data on the tissues in ICRP Publication 23. It was found that the tissue substitutes are suitable as the corresponding tissues defined in ICRP.

Journal Articles

Shielding analysis at the upper section of the accelerator-driven system

Sasa, Toshinobu; Yang, J. A.*; Oigawa, Hiroyuki

Radiation Protection Dosimetry, 116(1-4), p.256 - 258, 2005/12

 Times Cited Count:0 Percentile:100(Environmental Sciences)

The proton beam duct of the accelerator-driven system (ADS) acts a streaming path for spallation neutrons and photons and causes the activation of the magnets and other devices above the subcritical core. We have performed a streaming analysis at the upper section of the lead-bismuth target/cooled ADS (800MWth). MCNPX was used to calculate the radiation dose from streamed neutrons and photons through the beam duct. For the secondary photon production calculation, cross sections for several actinides were substituted for plutonium because of the lack of gamma production cross section. From the results of this analysis, the neutron dose from the beam duct is about 20 orders higher than that of the bulk shield. The magnets and shield plug were heavily irradiated by streaming neutrons according to the DCHAIN-SP analysis.

JAEA Reports

Proceedings of 6th Symposium on Advanced Photon Research; November 4th-5th, 2004, Kizu, Japan

Kansai Research Establishment

JAERI-Conf 2005-004, 243 Pages, 2005/06


This report consists of 55 contributed papers of the 6th Symposium on Advanced Photon Research, which was held at JAERI-Kansai in Kyoto on November 4-5, 2004. The numbers of speeches were 16, including 5 invited speeches and the numbers of poster presentations were 56, including the report of presentations and cooperative research and joint research performed in FY2003.

JAEA Reports

MVP/GMVP 2; General purpose Monte Carlo codes for neutron and photon transport calculations based on continuous energy and multigroup methods

Nagaya, Yasunobu; Okumura, Keisuke; Mori, Takamasa; Nakagawa, Masayuki

JAERI 1348, 388 Pages, 2005/06


To realize fast and accurate Monte Carlo simulation of neutron and photon transport problems, two vectorized Monte Carlo codes MVP and GMVP have been developed at JAERI. MVP is based on the continuous energy model and GMVP is on the multigroup model. Compared with conventional scalar codes, these codes achieve higher computation speed by a factor of 10 or more on vector supercomputers. Both codes have sufficient functions for production use by adopting accurate physics model, geometry description capability and variance reduction techniques. The first version of the codes was released in 1994. They have been extensively improved and new functions have been implemented. The major improvements and new functions are (1) capability to treat the scattering model expressed with File 6 of the ENDF-6 format, (2) time-dependent tallies, (3) reaction rate calculation with the pointwise response function, (4) flexible source specification, etc. This report describes the physical model, geometry description method used in the codes, new functions and how to use them.

Journal Articles

JENDL photonuclear data file

Kishida, Norio*; Murata, Toru*; Asami, Tetsuo*; Kosako, Kazuaki*; Maki, Koichi*; Harada, Hideo*; Lee, Y.*; Chang, J.*; Chiba, Satoshi; Fukahori, Tokio

AIP Conference Proceedings 769, p.199 - 202, 2005/05

Nuclear data for photonuclear reactions are required in the field of shielding design of high-energy electron accelerators and high-energy $$gamma$$-ray therapy. The JENDL Photonuclear Data File was prepared by a working group on nuclear data evaluations for photonuclear reactions in Japanese Nuclear Data Committee. From a survey of many literatures, it is difficult to construct the photonuclear data file by using only measured data, since there are not sufficient experimental data. We were therefore evaluating with theoretical calculations based on statistical nuclear reaction models. The photonuclear cross sections that are to be contained in the file are as follows: photoabsorption cross sections, yield cross sections and DDX for neutrons, protons, deuterons, tritons, $$^{3}$$He-particles and alpha-particles, and isotope production cross sections. For the actinide nuclides, photofission cross sections are also included. The maximum energy of incident photons is 140 MeV and stored are the photonuclear data for 68 nuclides from $$^{2}$$H to $$^{237}$$Np.

Journal Articles

Neutron cross-section evaluations for $$^{70,72,73,74,76}$$Ge

Iwamoto, Osamu; Herman, M.*; Mughabghab, S. F.*; Oblozinsk$'y$, P.*; Trkov, A.*

AIP Conference Proceedings 769, p.434 - 437, 2005/05

Entirely new evaluations for all the Ge isotopes, from thermal energy to 20 MeV, has been performed with focus on photon production. In the resonance region, parameters were improved considerably compared to earlier evaluations. In the fast region, code EMPIRE-2.19 was used. Validation was done against photon data on Fe and Nb. Isotopic evaluations for Ge were summed up and compared with available measurements on natural Ge. Various quantities related to photon production, showing strong dependence on neutron incident energy, are discussed.

JAEA Reports

Annual report of Kansai Research Establishment 2003; April 1, 2003 - March 31, 2004

Kansai Research Establishment

JAERI-Review 2004-030, 150 Pages, 2005/02


This report is the fifth issue of the annual report of Kansai Research Establishment, Japan Atomic Energy Research Institute. It covers status reports of R&D and results of experiments conducted at the Advanced Photon Research Center and the Synchrotron Radiation Research Center during the period from April 1, 2003 to March 31, 2004.

Journal Articles

Emission rates of CH/CD and C$$_{2}$$ spectral bands for hydrocarbon-loss-events measured in JT-60U divertor plasmas

Nakano, Tomohide; Tsuzuki, Kazuhiro; Higashijima, Satoru; Kubo, Hirotaka; Asakura, Nobuyuki

Europhysics Conference Abstracts (CD-ROM), 29C, 4 Pages, 2005/00

Emission rates of CH and C$$_2$$ spectral bands for CH$$_4$$, CD$$_4 and C$$_2$$H_6$$ loss events due to dissociation, ionization and transport were measured in JT-60U divertor plasmas. The obtained data were used for estimating the chemical sputtering yields by a spectroscopic technique. The CH$$_4$$ loss events over one CH photon emission was about 200 at electron temperatures between 30 eV and 70 eV. These values fell within the confidential band of the CD$$_4$$ one. The C$$_2$$H$$_6$$ loss events over one CH and one C$$_2$$ photon emission were, respectively, between 200 - 300 and between 600 - 1800, and their ratio between 3 - 6. On the assumption that only C$$_2$$H$$_6$$ among hydrocarbons generated by chemical sputtering emits the C$$_2$$ spectral bands, the intensity of the CH spectral bands originating from C$$_2$$H$$_6$$ is inferred from the intensity of C$$_2$$ spectral bands multiplied by the obtained ratio, resulting in higher than the measured CH intensity. This result indicates that dominant hydrocarbons generated by the chemical sputtering is not C$$_2$$H$$_6$$ but C$$_2$$H$$_4$$.

Journal Articles

Determination of detection efficiency curves of HPGe detectors on radioactivity measurement of volume samples

Saegusa, Jun; Kawasaki, Katsuya; Mihara, Akira; Ito, Mitsuo; Yoshida, Makoto

Applied Radiation and Isotopes, 61(6), p.1383 - 1390, 2004/12

 Times Cited Count:26 Percentile:14.56(Chemistry, Inorganic & Nuclear)

no abstracts in English

113 (Records 1-20 displayed on this page)