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Journal Articles

${it In situ}$ spectrometry of terrestrial gamma rays using portable germanium detectors in area of 80 km radius around the Fukushima Daiichi Nuclear Power Plant

Mikami, Satoshi; Tanaka, Hiroyuki*; Okuda, Naotoshi*; Sakamoto, Ryuichi*; Ochi, Kotaro; Uno, Kiichiro*; Matsuda, Norihiro; Saito, Kimiaki

Nihon Genshiryoku Gakkai Wabun Rombunshi, 20(4), p.159 - 178, 2021/12

In order to know the background radiation level where the area affected by the Fukushima Daiichi Nuclear Power Plant accident in 2011, terrestrial gamma rays had been measured by using portable germanium detectors repeatedly from 2013 through 2019, at 370 locations within 80 km radius area centered on the Fukushima Daiichi Nuclear Power Plant. Radioactive concentrations of Uranium 238, Thorium 232, Potassium 40 and kerma rates in air due to terrestrial gamma rays were obtained at those locations based on the method of ICRU report 53. Averaged concentrations of $$^{238}$$U, $$^{232}$$Th and $$^{40}$$K were 18.8, 22.7, 428 Bq/kg, respectively, and kerma rate in air over the area was found to be 0.0402 $$mu$$Gy/h. The obtained kerma rates in air were compared to those reported in literatures. It was confirmed that the data were correlated with each other, and were agreed within the range of their uncertainty. This is because the kerma rate in air due to terrestrial gamma rays is depend on geology. The similar trend to previous findings was observed that the kerma rate in air at locations geologically classified as Mesozoic era, Granite and Rhyolite were statistically significantly higher than the others.

Journal Articles

True coincidence summing correction for cylindrical volume samples in $$gamma$$-ray spectrometry

Yamada, Takashi*; Asai, Masato; Yonezawa, Chushiro*; Kakita, Kazutoshi*; Hirai, Shoji*

Radioisotopes, 69(9), p.287 - 297, 2020/09

We have confirmed that the commercially available Japanese `standard' gamma-ray analysis programs do not consider the effect of sample volume in calculating true coincidence summing (TCS) corrections, which results in underestimation of $$^{134}$$Cs radioactivity in cylindrical volume samples. In this work, we have developed and examined a practical TCS correction method for general Ge detectors which consider the effect of sample volume properly, and have confirmed that this method can reduce the $$^{134}$$Cs radioactivity underestimation to less than 1%.

Journal Articles

A Cubic CeBr$$_{3}$$ gamma-ray spectrometer suitable for the decommissioning of the Fukushima Daiichi Nuclear Power Station

Kaburagi, Masaaki; Shimazoe, Kenji*; Otaka, Yutaka*; Uenomachi, Mizuki*; Kamada, Kei*; Kim, K. J.*; Yoshino, Masao*; Shoji, Yasuhiro*; Yoshikawa, Akira*; Takahashi, Hiroyuki*; et al.

Nuclear Instruments and Methods in Physics Research A, 971, p.164118_1 - 164118_8, 2020/08

 Times Cited Count:3 Percentile:76.41(Instruments & Instrumentation)

Journal Articles

Measurements of thermal-neutron capture cross-section of cesium-135 by applying mass spectrometry

Nakamura, Shoji; Shibahara, Yuji*; Kimura, Atsushi; Iwamoto, Osamu; Uehara, Akihiro*; Fujii, Toshiyuki*

Journal of Nuclear Science and Technology, 57(4), p.388 - 400, 2020/04

 Times Cited Count:1 Percentile:23.13(Nuclear Science & Technology)

The thermal-neutron capture cross-section ($$sigma_{0}$$) and resonance integral(I$$_{0}$$) were measured for the $$^{135}$$Cs(n,$$gamma$$)$$^{136}$$Cs reaction by an activation method and mass spectrometry. We used $$^{135}$$Cs contained as an impurity in a normally available $$^{137}$$Cs standard solution. An isotope ratio of $$^{135}$$Cs and $$^{137}$$Cs in a standard $$^{137}$$Cs solution was measured by mass spectrometry to quantify $$^{135}$$Cs. The analyzed $$^{137}$$Cs samples were irradiated at the hydraulic conveyer of the research reactor in Institute for Integral Radiation and Nuclear Science, Kyoto University. Wires of Co/Al and Au/Al alloys were used as neutron monitors to measure thermal-neutron fluxes and epi-thermal Westcott's indices at an irradiation position. A gadolinium filter was used to measure the $$sigma_{0}$$, and a value of 0.133 eV was taken as the cut-off energy. Gamma-ray spectroscopy was used to measure induced activities of $$^{137}$$Cs, $$^{136}$$Cs and monitor wires. On the basis of Westcott's convention, the $$sigma_{0}$$ and I$$_{0}$$ values were derived as 8.57$$pm$$0.25 barn, and 45.3$$pm$$3.2 barn, respectively. The $$sigma_{0}$$ obtained in the present study agreed within the limits of uncertainties with the past reported value of 8.3$$pm$$0.3 barn.

Journal Articles

Guidance for ${it in situ}$ gamma spectrometry intercomparison based on the information obtained through five intercomparisons during the Fukushima mapping project

Mikami, Satoshi; Ishikawa, Daisuke*; Matsuda, Hideo*; Hoshide, Yoshifumi*; Okuda, Naotoshi*; Sakamoto, Ryuichi*; Saito, Kimiaki

Journal of Environmental Radioactivity, 210, p.105938_1 - 105938_7, 2019/12

 Times Cited Count:1 Percentile:10.3(Environmental Sciences)

Five intercomparisons of in situ $$gamma$$ spectrometry by 6-7 participating teams have been conducted between December 2011 and August 2015 at sites in Fukushima prefecture which affected by the fallout of FDNPS accident occurred in March 2011. The evaluated deposition densities agreed within 5-6% in terms of coefficient of variation (CV) for radiocesium ($$^{134}$$Cs and $$^{137}$$Cs), by our best achievement, and the ratio of $$^{134}$$Cs/$$^{137}$$Cs in deposition density agreed within 1-2% in CV, through five intercomparisons. These results guarantee the accuracy of the measurements of the mapping project. Two different methods for intercomparison were conducted: (1) sequential measurements at an identical point; and (2) simultaneous measurements in a narrow area within 3 m radius. In a comparison between the two methods at a site, no significant difference was observed between the results. The standard protocols for the two different intercomparison methods were proposed based on our experience.

Journal Articles

Activation measurement for thermal-neutron capture cross-section of Cesium-135

Nakamura, Shoji; Kimura, Atsushi; Iwamoto, Osamu; Shibahara, Yuji*; Uehara, Akihiro*; Fujii, Toshiyuki*

KURNS Progress Report 2018, P. 106, 2019/08

Under the ImPACT project, the neutron capture cross-section measurements of Cesium-135 ($$^{135}$$Cs) among the long-lived fission products have been performed at Kyoto University. This paper reports measurements of the thermal-neutron capture cross-section of $$^{135}$$Cs at the Kyoto University Research Reactor (KUR).

Journal Articles

Measurements of thermal-neutron capture cross-section and resonance integral of neptunium-237

Nakamura, Shoji; Kitatani, Fumito; Kimura, Atsushi; Uehara, Akihiro*; Fujii, Toshiyuki*

Journal of Nuclear Science and Technology, 56(6), p.493 - 502, 2019/06

 Times Cited Count:3 Percentile:57.07(Nuclear Science & Technology)

The thermal-neutron capture cross-section($$sigma_{0}$$)and resonance integral(I$$_{0}$$) were measured for the $$^{237}$$Np(n,$$gamma$$)$$^{238}$$Np reaction by an activation method. A method with a Gadolinium filter, which is similar to the Cadmium difference method, was used to measure the $$sigma_{0}$$ with paying attention to the first resonance at 0.489 eV of $$^{237}$$Np, and a value of 0.133 eV was taken as a cut-off energy. Neptunium-237 samples were irradiated at the pneumatic tube of the Kyoto University Research Reactor in Institute for Integral Radiation and Nuclear Science, Kyoto University. Wires of Co/Al and Au/Al alloys were used as monitors to determine thermal-neutron fluxes and epi-thermal Westcott's indices at an irradiation position. A $$gamma$$-ray spectroscopy was used to measure activities of $$^{237}$$Np, $$^{238}$$Np and neutron monitors. On the basis of Westcott's convention, the $$sigma_{0}$$ and I$$_{0}$$ values were derived as 186.9$$pm$$6.2 barn, and 1009$$pm$$90 barn, respectively.

Journal Articles

Challenges for enhancing Fukushima environmental resilience, 3; Development of measurement and evaluation techniques for the environmental radiation monitoring

Sanada, Yukihisa

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 59(7), p.418 - 422, 2017/07

no abstracts in English

Journal Articles

In situ $$gamma$$ spectrometry intercomparison in Fukushima, Japan

Mikami, Satoshi; Sato, Shoji*; Hoshide, Yoshifumi*; Sakamoto, Ryuichi*; Okuda, Naotoshi*; Saito, Kimiaki

Hoken Butsuri, 50(3), p.182 - 188, 2015/09

Intercomparison of in situ $$gamma$$ spectrometry was organized at a site contaminated by the radioactive fallout that originated from the Fukushima Dai-ichi Nuclear Power Plant accident. This intercomparison was conducted by eight teams from four different institutions, which have contributed to the government-led project to construct distribution maps of radionuclides deposited on the ground soil. The resultant $$^{134}$$Cs and $$^{137}$$Cs inventories evaluated by the participants agreed within 6% of the coefficient of variation, after correction for inhomogeneous distribution of the air dose rate. The evaluated $$^{40}$$K inventories agreed within 4% of the coefficient of variation. The authors estimated that these results were in good agreement for creating distribution maps of the radionuclide inventory in the ground soil.

Journal Articles

LaCl$$_{3}$$(Ce) scintillation detector applications for environmental $$gamma$$-ray measurements of low to high dose rates

Tsutsumi, Masahiro; Tanimura, Yoshihiko

Nuclear Instruments and Methods in Physics Research A, 557(2), p.554 - 560, 2006/02

 Times Cited Count:12 Percentile:65.95(Instruments & Instrumentation)

A new cerium-doped LaCl$$_{3}$$(Ce) scintillator is evaluated with respect to the application in environmental $$gamma$$-ray dosimetry and spectrometry. The scintillator is very attractive for $$gamma$$-ray spectrometry in the case of high count rate, because it has excellent energy resolution and fast decay time. The performance characteristics of a scintillator with a 25.4 mm $$times$$ 25.4 mm LaCl$$_{3}$$(Ce) crystal are studied and compared to those of a NaI(Tl) scintillator with the same size crystal. Acquired pulse-height spectra are converted to dose rates by using the G(E) function method. Though the LaCl$$_{3}$$(Ce) crystal itself produces a rather high background in the crystal itself, the scintillator provides good energy information and dose-rate readings from low to high-level (several mGy/h) by subtracting the self-background. The properties of LaCl$$_{3}$$(Ce) scintillator suggest that the scintillator could be a promising candidate for monitoring at high-dose levels as in emergencies, as well as at ordinary levels of background radiation.

Journal Articles

Centralized radioactivity measurement system for radiation control in Tokai research establishment of JAERI

Kawasaki, Katsuya

Hoken Butsuri, 40(1), p.56 - 60, 2005/03

The centralized radioactivity measurement system has been used to carry out intensively measurements of a large number and variety of samples that are necessary for the control of radioactivity in the facilities of the JAERI Tokai Establishment and its environment. The operation of the system started in 1981, and presently the system processes more than 20,000 samples a year. However, the computers of the system have aged so much that the manufacturer's support and stable operation are no longer sure. Therefore, we renewed and restructured the computer system in 2003. A client-server system was adopted in the new system. The information of samples can be registered through the intranet. The clients can also confirm the progress of processing of their samples and browse the analytical results from their own computers. The renewed system can provide some convenience functions to the clients. This report is introduced about the centralized radioactivity measurement system.

JAEA Reports

Renewal of centralized radioactivity measurement system for radiation control

Kawasaki, Katsuya; Mochizuki, Kaoru*; Suzuki, Takehiko; Kinouchi, Nobuyuki

JAERI-Tech 2004-070, 50 Pages, 2004/12

JAERI-Tech-2004-070.pdf:18.19MB

The centralized radioactivity measurement system has been used to carry out intensively measurements of a large number and variety of samples that are necessary for the control of radioactivity in the facilities of the JAERI Tokai Establishment and its environment. The operation of the system started in 1981, and presently the system processes more than 20,000 samples a year. However, the computers of the system have aged so much that the manufacturer's support and stable operation are no longer sure. Therefore, we renewed and restructured the computer system in 2003. A client-server system was adopted in the new system. The information of samples can be registered through the intranet. The clients can also confirm the progress of processing of their samples and browse the analytical results from their own computers. The renewed system can provide some convenience functions to the clients.

Journal Articles

Density measurement of molten NdCl$$_3$$-NaCl and NdCl$$_3$$-KCl system by $$gamma$$ ray attenuation

Sato, Tadashi; Okamoto, Yoshihiro; Ogawa, Toru

Journal of Nuclear Science and Technology, 39(Suppl.3), p.635 - 637, 2002/11

Densities of molten chlorides mixtures of NdCl$$_3$$-NaCl and NdCl$$_3$$-KCl systems have been measured using $$gamma$$-ray attenuation method as a function of temperature. Gamma ray spectra of Ho-166m radiation source were taken before and after passing through the molten chlorides in a quartz cell by a Ge-detector coupled with muluti-channel analyzer. The density was calculated with observed attenuation factor, cross section data of photons for relevant elements and length of the cell. The measured densities of molten NdCl$$_3$$-NaCl and NdCl$$_3$$-KCl were compared with literature data by dilatometric method.

Journal Articles

Retention of fission product cesium in ZrC coated fuel particles for high-temperature gas-cooled reactors

Minato, Kazuo; Ogawa, Toru; Koya, Toshio; Sekino, Hajime; Tomita, Takeshi

Journal of Nuclear Materials, 279(2-3), p.181 - 188, 2000/06

 Times Cited Count:32 Percentile:88.17(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Evaluation of peak-to-total ratio for germanium detectors

*; Oi, Yoshihiro; Taki, Mitsumasa; Kawasaki, Katsuya; Yoshida, Makoto

Applied Radiation and Isotopes, 50(6), p.1057 - 1061, 1999/00

 Times Cited Count:6 Percentile:46.57(Chemistry, Inorganic & Nuclear)

no abstracts in English

JAEA Reports

Natural background Gamma-ray spectrum; List of Gamma-rays ordered in energy from natural radionuclides

*; ; Kitao, Kensuke*

JAERI-Data/Code 98-008, 73 Pages, 1998/03

JAERI-Data-Code-98-008.pdf:26.34MB

no abstracts in English

JAEA Reports

Sample preparation and characterization of technetium metal

Minato, Kazuo; Serizawa, Hiroyuki; Fukuda, Kosaku; Ito, Mitsuo

JAERI-Research 97-077, 17 Pages, 1997/10

JAERI-Research-97-077.pdf:1.09MB

no abstracts in English

Journal Articles

Modified conversion ratio measurement in light water-moderated UO$$_{2}$$ lattices

Nakajima, Ken;

Nuclear Technology, 113, p.375 - 379, 1996/03

 Times Cited Count:5 Percentile:46.08(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Gamma spectrometry of TMI-2 debris

Uetsuka, Hiroshi; Nagase, Fumihisa; *

JAERI-Research 95-084, 36 Pages, 1995/11

JAERI-Research-95-084.pdf:1.32MB

no abstracts in English

Journal Articles

Dose intercomparison experiment for gamma rays and 3-MeV electrons by mailing dosimetry using free-radical dosimeters

S.R.Nilekani*; G.R.Narayan*; B.Suseela*; R.M.Bhat*; B.L.Gupta*; Kojima, Takuji; Takizawa, Haruki; Sunaga, Hiromi; Tanaka, Ryuichi

Applied Radiation and Isotopes, 46(3), p.205 - 207, 1995/00

 Times Cited Count:5 Percentile:58.92(Chemistry, Inorganic & Nuclear)

no abstracts in English

32 (Records 1-20 displayed on this page)