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Journal Articles

Improvement in the elution performance of an N,N,N',N-tetraoctyl diglycolamide impregnated extraction chromatography adsorbent using neodymium via micro-particle-induced X-ray emission analysis

Takahatake, Yoko; Watanabe, So; Arai, Tsuyoshi*; Sato, Takahiro*; Shibata, Atsuhiro

Applied Radiation and Isotopes, 196, p.110783_1 - 110783_5, 2023/06

 Times Cited Count:0 Percentile:0.01(Chemistry, Inorganic & Nuclear)

Journal Articles

Accurate and precise measurement of uranium content in uranium trioxide by gravimetry; Comparison with isotope dilution mass spectrometry and its uncertainty estimation

Yamamoto, Masahiko; Horigome, Kazushi; Kuno, Takehiko

Applied Radiation and Isotopes, 190, p.110460_1 - 110460_7, 2022/12

 Times Cited Count:1 Percentile:33.72(Chemistry, Inorganic & Nuclear)

Gravimetric measurement of U content in UO$$_{3}$$ with ignition in the air has been investigated. The ignition temperature, ignition time and aliquot sample mass are optimized as 900$$^{circ}$$C, 60 minutes, and 1 g, respectively. The method is validated by IDMS with uncertainty estimation. The obtained result by gravimetry is 0.78236$$pm$$0.00051 g/g (k=2) and agreed with IDMS value within its uncertainty. It has been found that U in UO$$_{3}$$ can be measured accurately and precisely by gravimetry.

Journal Articles

New data processing method for nuclear material measurement using pulsed neutrons

Komeda, Masao; Toh, Yosuke

Applied Radiation and Isotopes, 188, p.110391_1 - 110391_6, 2022/10

 Times Cited Count:0 Percentile:0.01(Chemistry, Inorganic & Nuclear)

Journal Articles

Improved experimental evaluation and model validation of a $$^{252}$$Cf irradiator for delayed gamma-ray spectroscopy applications

Tohamy, M.*; Abbas, K.*; Nonneman, S.*; Rodriguez, D.; Rossi, F.

Applied Radiation and Isotopes, 173, p.109694_1 - 109694_7, 2021/07

 Times Cited Count:5 Percentile:66.98(Chemistry, Inorganic & Nuclear)

Journal Articles

Supercritical water pretreatment method for analysis of strontium and uranium in soil (Andosols)

Nagaoka, Mika; Fujita, Hiroki; Aida, Taku*; Guo, H.*; Smith, R. L. Jr.*

Applied Radiation and Isotopes, 168, p.109465_1 - 109465_6, 2021/02

 Times Cited Count:0 Percentile:0.01(Chemistry, Inorganic & Nuclear)

The radioactivities in the environmental samples are analyzed to monitor the nuclear power facilities. The pretreatment of radioactive nuclides of alpha and beta emitters in the environmental samples is performed with acid to decompose organic matter and extract object nuclide such as $$^{90}$$Sr, U and Pu. However, the pretreatment methods are time-consuming and used many concentrated acid solutions that are unsafe and hazardous. Therefore, we develop to the new pretreatment method using supercritical water instead of acid. Hydrothermal pretreatment of soils (Andosols) from Ibaraki prefecture (Japan) was used to improve methods for monitoring radioactive Sr and U. Calcined samples were pretreated with subcritical or supercritical water (SCW) followed by extraction with 0.5 M HNO$$_{3}$$ solutions. With SCW pretreatment, recoveries of Sr and U were 70% and 40%, respectively. Experimental recoveries obtained can be described by a linear relationship in water density. The proposed method is robust and can lower environmental burden of routine analytical protocols.

Journal Articles

Study of charged particle activation analysis, 2; Determination of boron concentration in human blood samples

Ikebe, Yurie*; Oshima, Masumi*; Bamba, Shigeru*; Asai, Masato; Tsukada, Kazuaki; Sato, Tetsuya; Toyoshima, Atsushi*; Bi, C.*; Seto, Hirofumi*; Amano, Hikaru*; et al.

Applied Radiation and Isotopes, 164, p.109106_1 - 109106_7, 2020/10

 Times Cited Count:2 Percentile:24.76(Chemistry, Inorganic & Nuclear)

Boron Neutron Capture Therapy (BNCT) is a radiotherapy for the treatment of intractable cancer. In BNCT precise determination of $$^{10}$$B concentration in whole blood sample before neutron irradiation is crucial for control of the neutron irradiation time and the neutron dosimetry. We have applied the Charged Particle Activation Analysis (CPAA) to non-destructive and accurate determination of $$^{10}$$B concentration in whole blood sample. The experiment was performed at JAEA Tandem Accelerator using an 8 MeV proton beam. The 478 keV $$gamma$$ ray of $$^{7}$$Be produced in the $$^{10}$$B(p,$$alpha$$)$$^{7}$$Be reaction was used to quantify the $$^{10}$$B, and $$gamma$$ rays of $$^{56}$$Co originating from the reaction with Fe in blood was used to normalize the $$gamma$$-ray intensity. The results demonstrated that the present CPAA method can be applied to the determination of the $$^{10}$$B concentration in the blood sample.

Journal Articles

Corrigendum to "Model design of a compact delayed gamma-ray moderator system using $$^{252}$$Cf for safeguards verification measurements" [Appl. Radiat. Isot. 148C (2019) 114-125]

Rodriguez, D.; Rossi, F.; Takahashi, Tone; Seya, Michio*; Koizumi, Mitsuo

Applied Radiation and Isotopes, 159, P. 109083_1, 2020/05

 Times Cited Count:0 Percentile:1.52(Chemistry, Inorganic & Nuclear)

Journal Articles

Development of an online measurement system using an alpha liquid scintillation counter and a glass-based microfluidic solvent extraction device for plutonium analysis

Yamamoto, Masahiko; Taguchi, Shigeo; Do, V. K.; Kuno, Takehiko; Surugaya, Naoki

Applied Radiation and Isotopes, 152, p.37 - 44, 2019/10

 Times Cited Count:5 Percentile:67.25(Chemistry, Inorganic & Nuclear)

An online measurement system using an alpha liquid scintillation counter ($$alpha$$-LSC) coupled to microchip solvent extraction has been developed. A flow-through cell of $$alpha$$-LSC has been prepared by packing PTFE tube into glass tube to combine microchip. Two-phase flow in microchannel has been stabilized by using coiled tube. The Pu in organic phase has been mixed with scintillation cocktail by T-junction connectors. The system separates and detects Pu by online with detection limit of 6.5 Bq/mL, generating only $$mu$$L-level wastes.

Journal Articles

On-line rapid purification of [$$^{13}$$N]N$$_2$$ gas for visualization of nitrogen fixation and translocation in nodulated soybean

Yin, Y.-G.*; Ishii, Satomi*; Suzui, Nobuo*; Igura, Masato*; Kurita, Keisuke; Miyoshi, Yuta*; Nagasawa, Naotsugu*; Taguchi, Mitsumasa*; Kawachi, Naoki*

Applied Radiation and Isotopes, 151, p.7 - 12, 2019/09

 Times Cited Count:6 Percentile:56.35(Chemistry, Inorganic & Nuclear)

Accurate analysis of N fixation in leguminous crops requires determination of N utilization within an intact plant$$;$$ however, most approaches require tissue disassembly. We developed a simple and rapid technique to generate high-purity and high-yield [$$^{13}$$N]N$$_2$$ gas and obtained real-time images of N fixation in an intact soybean plant. The purification efficiency was $$sim$$ 81.6% after decay correction.

Journal Articles

Rapid analytical method of $$^{90}$$Sr in urine sample; Rapid separation of Sr by phosphate co-precipitation and extraction chromatography, followed by determination by triple quadrupole inductively coupled plasma mass spectrometry (ICP-MS/MS)

Tomita, Jumpei; Takeuchi, Erina

Applied Radiation and Isotopes, 150, p.103 - 109, 2019/08

 Times Cited Count:10 Percentile:80.76(Chemistry, Inorganic & Nuclear)

A rapid analytical method for determining $$^{90}$$Sr in urine samples (1-2 L) was developed to assess the internal exposure of workers in a radiological emergency. Strontium in a urine sample was rapidly separated by phosphate co-precipitation, followed by extraction chromatography with a tandem column of Pre-filter, TRU and Sr resin, and the $$^{90}$$Sr activity was determined by ICP-MS/MS. Measurement in the MS/MS mode with an O$$_{2}$$ reaction gas flow rate 1 mL min$$^{-1}$$ showed no tailing of $$^{88}$$Sr at m/z = 90 up to 50 mg-Sr L$$^{-1}$$. The interferences of Ge, Se and Zr at m/z = 90 were successfully removed by chemical separation. This analytical method was validated by the results of the analyses of synthetic urine samples (1.2-1.6 L) containing a known amount of $$^{90}$$Sr along with 1 mg of each of Ge, Se, Sr and Zr. The turnaround time for analysis was about 10 h, and the detection limit of $$^{90}$$Sr was approximately 1 Bq per urine sample.

Journal Articles

Model design of a compact delayed gamma-ray moderator system using $$^{252}$$Cf for safeguards verification measurements

Rodriguez, D.; Rossi, F.; Takahashi, Tone; Seya, Michio; Koizumi, Mitsuo

Applied Radiation and Isotopes, 148, p.114 - 125, 2019/06

 Times Cited Count:5 Percentile:49.54(Chemistry, Inorganic & Nuclear)

Journal Articles

Development of clearance verification equipment for uranium-bearing waste

Yokoyama, Kaoru; Ohashi, Yusuke

Applied Radiation and Isotopes, 145, p.19 - 23, 2019/03

 Times Cited Count:5 Percentile:49.54(Chemistry, Inorganic & Nuclear)

Dismantled materials generated from nuclear facilities are reused or directed to repository sites. If scrap metals with complicated shapes can be cleared, the amounts of radioactive waste can be reduced. A clearance verification system is constructed to determine the amount of uranium in decontaminated metals in a drum using the 1.001 MeV gamma rays of $$^{rm 234m}$$Pa, produced in the decay of $$^{238}$$U. The experimental study with simulated waste drums demonstrated that the quantification errors of uranium fall within 25% for 0.5g of uranium.

Journal Articles

Development and application of a method for discriminating the influence of radon progenies in air from aerial radiation monitoring data

Hirouchi, Jun; Nishizawa, Yukiyasu*; Urabe, Yoshimi*; Shimada, Kazumasa; Sanada, Yukihisa; Munakata, Masahiro

Applied Radiation and Isotopes, 141, p.122 - 129, 2018/11


 Times Cited Count:1 Percentile:11.6(Chemistry, Inorganic & Nuclear)

Journal Articles

Feasibility study of large-scale production of iodine-125 at the high temperature engineering test reactor

Ho, H. Q.; Honda, Yuki*; Hamamoto, Shimpei; Ishii, Toshiaki; Fujimoto, Nozomu*; Ishitsuka, Etsuo

Applied Radiation and Isotopes, 140, p.209 - 214, 2018/10

 Times Cited Count:3 Percentile:30.45(Chemistry, Inorganic & Nuclear)

Journal Articles

Proposal of a neutron transmutation doping facility for n-type spherical silicon solar cell at high-temperature engineering test reactor

Ho, H. Q.; Honda, Yuki; Motoyama, Mizuki*; Hamamoto, Shimpei; Ishii, Toshiaki; Ishitsuka, Etsuo

Applied Radiation and Isotopes, 135, p.12 - 18, 2018/05

 Times Cited Count:7 Percentile:58.44(Chemistry, Inorganic & Nuclear)

Journal Articles

Evaluation of the accuracy of mono-energetic electron and beta-emitting isotope dose-point kernels using particle and heavy ion transport code system: PHITS

Shiiba, Takuro*; Kuga, Naoya*; Kuroiwa, Yasuyoshi*; Sato, Tatsuhiko

Applied Radiation and Isotopes, 128, p.199 - 203, 2017/10

 Times Cited Count:7 Percentile:61.68(Chemistry, Inorganic & Nuclear)

We calculated scaled dose point kernels (DPKs) for mono-energetic electron in water (0.015, 0.1, 1.0, and 2.0 MeV) and compact bone (0.010 and 1 MeV) using the latest version of PHITS. Furthermore, we calculated beta-emitting isotopes ($$^{89}$$Sr, $$^{90}$$Y, $$^{131}$$I) DPKs in both water and bone. The simulated results of mono-energetic electron and beta-emitting DPKs were compared with those in literature using different MC codes, such as EGSnrc, GATE6.0, MCNP4C, and FLUKA. All mono-energetic and beta-emitting isotope DPKs calculated using PHITS, both in water and compact bone, were in good agreement with those in literature using other MC codes. The differences were $$<$$4% for all mono-energetic electron and beta-emitting isotope DPKs in both water and bone. PHITS provided reliable mono-energetic electron and beta-emitting isotope scaled DPKs in both water and compact bone for patient-specific dosimetry.

Journal Articles

Temporal variation of dose rate distribution around the Fukushima Daiichi Nuclear Power Station using unmanned helicopter

Sanada, Yukihisa; Orita, Tadashi; Torii, Tatsuo

Applied Radiation and Isotopes, 118, p.308 - 316, 2016/12

 Times Cited Count:26 Percentile:93.42(Chemistry, Inorganic & Nuclear)

An unmanned helicopter monitoring system (UHMS) was developed to survey the environmental effect of radioactive cesium scattered as a result of the Fukushima Daiichi Nuclear Power Station accident. The UHMS was mainly used to monitor the area surrounding the Fukushima Daiichi Nuclear Power Station six times from 2012 to 2015. Quantitative changes in the radioactivity distribution trend were revealed from the results of these monitorings runs.

Journal Articles

Design and burn-up analyses of new type holder for silicon neutron transmutation doping

Komeda, Masao; Arai, Masaji; Tamai, Kazuo*; Kawasaki, Kozo*

Applied Radiation and Isotopes, 113, p.60 - 65, 2016/07

 Times Cited Count:2 Percentile:19.85(Chemistry, Inorganic & Nuclear)

We designed and fabricated a new type holder that achieved uniform doping under long-term use at JRR-3. The new type holder uses an aluminum alloy and B$$_{4}$$C particles as filter materials to ensure uniform vertical flux distribution. Although the amount of filter material decreases with long-term use, it was found that the doping distribution did not change by much until 800 h. The lifetime of the new type holder (of the order of hundreds of hours) depends mainly on the amount of trapped radioactive isotopes. This indicates that the decrease in filtering ability over the filter's lifetime is not significant. The filtering ability remains stable for a long time, and the difference in the vertical doping distribution is 1.08 at 1600 h and 1.18 at 4000 h. The irradiation efficiency is expected to increase by 1.7 times when using the new type holder.

Journal Articles

Application of support vector machine to rapid classification of uranium waste drums using low-resolution $$gamma$$-ray spectra

Hata, Haruhi; Yokoyama, Kaoru; Ishimori, Yuu; Ohara, Yoshiyuki; Tanaka, Yoshio; Sugitsue, Noritake

Applied Radiation and Isotopes, 104, p.143 - 146, 2015/10

 Times Cited Count:9 Percentile:64.82(Chemistry, Inorganic & Nuclear)

We investigated the feasibility of using support vector machine (SVM), a computer learning method, to classify uranium waste drums as natural uranium or reprocessed uranium based on their origins. The method was trained using 12 training datasets were used and tested on 955 datasets of $$gamma$$-ray spectra obtained with NaI(Tl) scintillation detectors. The results showed that only 4 out of 955 test datasets were different from the original labels-one of them was mislabeled and the other three were misclassified by SVM. These findings suggest that SVM is an effective method to classify a large quantity of data within a short period of time. Consequently, SVM is a feasible method for supporting the scaling factor method and as a supplemental tool to check original labels.

Journal Articles

Method for determining individual deposition velocities of radon progeny

Angell, C.; Pedretti, M.*; Norman, E. B.*

Applied Radiation and Isotopes, 98, p.34 - 39, 2015/04

 Times Cited Count:2 Percentile:17.75(Chemistry, Inorganic & Nuclear)

110 (Records 1-20 displayed on this page)