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Morishita, Yuki
Isotope News, (803), p.38 - 42, 2026/02
In this study, we developed an alpha ray imaging detector for the in-situ measurement of
Pu and
Np to identify alpha nuclides in real time on-site. The alpha ray imaging detector developed in this study was brought to Savannah River National Laboratory (SRNL) in the United States, where measurements were performed on actual
Pu and
Np oxide samples. These measurements confirmed the effectiveness of in-situ detection of
Pu and
Np. We also developed a detector that can directly measure alpha contamination inside pipes. We confirmed the detector's ability to distinguish between alpha and beta rays and evaluated its basic characteristics.
Koizumi, Mitsuo; Yogo, Akifumi*
Isotope News, (802), p.11 - 14, 2025/12
no abstracts in English
Yokozuka, Eri*; Seito, Hajime*; Oka, Toshitaka; Kumagai, Yuta; Nagasawa, Naotsugu*
Isotope News, (801), p.46 - 48, 2025/10
no abstracts in English
Sato, Kaoru
Isotope News, (801), p.6 - 9, 2025/10
In 2012, ICRP recommended the latest scientific knowledge on radiation protection for the stem cells. Body size affects exposure doses, so the differences in body sizes between Japanese and Caucasians must be considered in dose assessments. Previously, there were no adult Japanese human models incorporating the stem cell regions. Therefore, we developed polygon mesh-type human models of the average adult Japanese male (JPM) and female (JPF) to analyze exposure doses considering Japanese body characteristics. We have completed these models by defining stem cells within organs like the alimentary tracts, urinary bladder, and lens, using image processing. The JPM and JPF are the only human models that can evaluate exposure doses to organs and its stem cells, considering the body characteristics of the Japanese. They are expected to be useful for optimizing exposure management in the medical and nuclear fields. This paper provides an overview of the JPM and JPF.
Jinno, Satoshi; Matsubara, Akihiro*; Fujita, Natsuko; Kimura, Kenji
Isotope News, (801), p.2 - 5, 2025/10
Accelerator Mass Spectrometry (AMS) is widely used in archaeology and geosciences, and since the 2000s, downsized AMS with an acceleration voltage of 200
500 kV has been put to practical use mainly for
C dating. However, the beam divergence due to collisions with gases increases at accelerating energies below 100 keV, resulting in a decrease in transmittance. Therefore, we are investigating charge conversion and dissociation of interfering molecules on KCl, SnTe, and Au crystal surfaces using the crystal surface stripper method we have developed. In this article, we report on the position of our research and the current progress.
Kumada, Takayuki; Iwahara, Daisuke*
Isotope News, (798), p.26 - 27, 2025/04
no abstracts in English
Yamaguchi, Akiko; Takahashi, Yoshio*; Okumura, Masahiko
Isotope News, (796), p.21 - 23, 2024/12
Clay minerals are abundant in soils and control the environmental behavior of various elements because they adsorb many cations. Since the strength of adsorption of clay minerals depends on the adsorption structure at the molecular level, a systematic understanding of what determines the adsorption structure at the molecular level is important. In this study, we systematically elucidated the adsorption structures of many cations, including radium, using extensive X-ray absorption fine structure (EXAFS) measurements and first-principles simulations. The results show that the size and hydration enthalpy of adsorbed ions are important in determining the adsorption structure.
Harjo, S.
Isotope News, (793), p.13 - 16, 2024/06
no abstracts in English
Uchibori, Akihiro; Okano, Yasushi
Isotope News, (793), p.32 - 35, 2024/06
The design of a containment vessel in a sodium-cooled fast reactor was optimized from simulation on the hypothetical severe accident including sodium leakage and combustion. The simulation method is one of the base technologies of the design optimization system, ARKADIA. The simulation was performed on the different design conditions including volume of the containment vessel and the safety equipment as optimization parameters. The iterative simulation successfully found that the safety under this accident was kept even in the downsized containment vessel by selecting an effective safety equipment. This study demonstrated that the developed method has basic capability for design optimization in ARKADIA.
,
, and X-ray spectrum analysisOshima, Masumi*; Goto, Jun*; Hayakawa, Takehito*; Asai, Masato; Kin, Tadahiro*; Shinohara, Hirofumi*
Isotope News, (790), p.19 - 23, 2023/12
When analyzing samples that contain many radionuclides at various concentrations, such as radioactive waste or fuel debris, it is difficult to apply general spectrum analysis methods and is necessary to chemically separate each nuclide before quantifying it. The chemical separation is especially essential for analysis using a liquid scintillation counter (LSC). In this report, the authors explain the newly developed spectral determination method (SDM) in which the entire spectrum is fitted to quantify radioactivity of nuclides mixed in a sample. By applying the SDM to
- and X-ray spectrum measured by LSC and
-ray spectrum measured by Ge detector simultaneously, the authors demonstrated that radioactivity of 40 radionuclides mixed in a sample at concentrations varying by two orders could be quantified, which is useful to simplify chemical separation process in radionuclide quantification.
Yamaguchi, Akiko; Okumura, Masahiko; Takahashi, Yoshio*
Isotope News, (789), p.20 - 23, 2023/10
Radium is a radioactive element produced from uranium and thorium and is important for environmental contamination issues around uranium mines and for geological disposal. In addition, radium is used in radiometric dating and cancer therapy, making it important not only in environmental chemistry but also in many other fields, including geochemistry and nuclear medicine. However, because radium is a radioactive element with no stable isotopes, spectroscopic measurement of radium is difficult, and little information at the molecular level has been obtained so far. In this study, we have clarified the molecular-level information of hydrated radium for the first time in the world by combining extended X-ray absorption fine structure (EXAFS) measurements and first-principles molecular dynamics simulations.
Tsubota, Yoichi
Isotope News, (787), p.28 - 31, 2023/06
In the fuel debris retrieval process during the decommissioning of the Fukushima Daiichi Nuclear Power Station (1F), radioactive particulates are generated in the primary containment vessel (PCV). Particulates containing
nuclides (
-aerosols), which have a particularly large internal exposure effect, are important to be monitored in addition to confinement measures in the PCV. The research group of the Japan Atomic Energy Agency (JAEA) summarized the four requirements for measuring
-aerosols in the harsh environment of the 1F-PCV as follows: "reliable operation in a high humidity environment", "measurement of
-aerosols without using filter paper", "measurement of high concentration of
-aerosols", and "selective measurement of
-aerosols". The IAAM was developed as an instrument that satisfies these four criteria. The IAAM was developed as an "in-situ"
-aerosol measurement device that combines air heating, a flat-type flow path, direct measurement of
-aerosol, usage of multi-channel photomultiplier tube, and an optimized scintillator thickness. Performance verification tests have demonstrated that the IAAM can be used for real-time measurement of
-aerosol concentration in air, and that it can measure more than 30 times of
-aerosol concentration expected in the 1F-PCV. In the future, we will continue to verify the measurement of
-aerosol concentration at various sites and aim to apply the system to such sites.
Furuta, Takuya
Isotope News, (787), p.20 - 23, 2023/06
Carbon ion radiotherapy has an advantage over conventional radiotherapy such that its superior dose concentration on the tumor helps to reduce unwanted dose to surrounding normal tissues. Nevertheless, a little dose to normal tissues, which is a potential risk of secondary cancer, is still unavoidable. In the current dose assessment, however, only assessment around target volume is performed for the tumor control and prevention of acute radiation injury of fatal organs. We therefore developed a system called RT-PHITS for CIRT to reproduce the carbon ion radiotherapy including the production and transport of secondary particles based on treatment planning data using PHITS. Using this system, whole-body dose assessment of patients in the past carbon ion radiotherapy can be performed. By comparing the dose assessment to the epidemiologic records of the patients, the relation between dose exposure of non-target organs and incidence of side effects such as secondary cancer will be elucidated.
Miyamoto, Yutaka; Suzuki, Daisuke; Tomita, Ryohei; Tomita, Jumpei; Yasuda, Kenichiro
Isotope News, (786), p.22 - 25, 2023/04
no abstracts in English
Yoshitomi, Hiroshi
Isotope News, (786), p.26 - 29, 2023/04
no abstracts in English
Matsuda, Shohei; Yokoyama, Keiichi
Isotope News, (786), p.6 - 9, 2023/04
no abstracts in English
Nishio, Katsuhisa
Isotope News, (785), p.36 - 40, 2023/02
no abstracts in English
Nakayama, Hiromasa; Onodera, Naoyuki; Satoh, Daiki
Isotope News, (785), p.20 - 23, 2023/02
We developed the local-scale high-resolution atmospheric dispersion and dose assessment system (LHADDAS) for safety and consequence assessment of nuclear facilities and emergency response to nuclear accidents or deliberate releases of radioactive materials in built-up urban areas. This system comprises three parts, namely, preprocessing of input files, main calculation by a local-scale high-resolution atmospheric dispersion model using large-eddy simulation (LOHDIM-LES) or a real-time urban dispersion simulation model based on a lattice Boltzmann method (CityLBM), and postprocessing of dose calculation by a simulation code powered by lattice dose-response functions (SIBYL). LHADDAS has a broad utility and performs excellently in (1) simulating turbulent flows, plume dispersion, and dry deposition under realistic meteorological conditions; (2) simulating real-time tracer dispersion using a locally mesh-refined lattice Boltzmann method; and (3) estimating the air dose rates of radionuclides from air concentrations and surface deposition in consideration of the influence of individual buildings and structures. This system is promising for use in safety assessment of nuclear facilities (as an alternative to wind tunnel experiments), detailed pre/post-analyses of local-scale radioactive plume dispersion in case of nuclear accidents, and quick response to emergency situations resulting from deliberate release of radioactive materials by terrorist attacks in central urban district areas.
Ota, Masakazu; Koarashi, Jun
Isotope News, (784), p.28 - 31, 2022/12
In forests affected by the Fukushima Daiichi Nuclear Power Plant accident, trees became contaminated with
Cs. However,
Cs transfer processes determining the tree contamination (particularly for stem wood, a prominent commercial resource) remain insufficiently understood. We propose a model (SOLVEG-R) for simulating dynamic behavior of
Cs in a forest tree-litter-soil system and applied it to contaminated forests of cedar plantation and natural oak stand in Fukushima to elucidate relative impact of distinct
Cs transfer processes determining the tree contamination. The transfer of
Cs to the trees occurred mostly (
99%) through surface uptake of
Cs trapped by needles and bark during the fallout. Root uptake of soil
Cs was several orders of magnitude lower than the surface uptake over a 50-year period following the accident. As a result, internal contamination of the trees proceeded through an enduring recycling (translocation) of
Cs absorbed on the tree surface. A significant surface uptake of
Cs through bark was suggested, contributing to 100% (leafless oak tree) and 30% (foliated cedar tree; the remaining uptake occurred at needles) of the total uptake by the trees. It was suggested that the activity concentration of
Cs in stem wood of the trees at these sites are currently (as of 2021) decreasing by 3% per year, mainly through radioactive decay of
Cs and partly through dilution effect from tree growth.