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-isosaccharinic acidKitamura, Akira; Sekioka, Yasushi*
no journal, ,
Solubility of palladium and tin has been experimentally investigated in the presence of -isosaccharinic acid (ISA). The obtained solubility increased with increasing concentration of ISA, especially for palladium.
Yamamoto, Akio*; Endo, Tomohiro*; Tada, Kenichi
no journal, ,
This presentation explains the multi-group generation module. This module generates multi-group cross section library from the ACE file which is the cross section library for continuous energy Monte Carlo calculation codes. The processing results of this function are compared with those of NJOY to verify this module.
Kawaguchi, Munemichi
no journal, ,
In decommissioning sodium-cooled fast reactors, the thermal decomposition behavior of tritium is important from the viewpoint of reducing the exposed radiation for the operators during dismantling of the cold trap equipment. In this study, the thermal decomposition temperature and rate of sodium hydride (95.3%, Sigma-Aldrich) were estimated from the TG-DTA measurements. The change of the chemical composition for the thermal decomposition was measured with X-Ray Diffraction analysis.
Komeda, Masao; Toh, Yosuke; Tanabe, Kosuke*
no journal, ,
no abstracts in English
AmNakamura, Shoji; Shibahara, Yuji*; Endo, Shunsuke; Kimura, Atsushi
no journal, ,
Research and development were made for accuracy improvement of neutron capture cross-section data on Am among minor actinides. First, the emission probabilities of decay 
-rays were obtained with high accuracy, and the amount of the ground state of 
Am produced by reactor neutron irradiation of Am was examinded by-ray measurement. Next, the total amount of isomer and ground states was examoned by -ray measurement. This presentation will give the details of the measurenmets and the results of the neutron capture cross-sections of Am.
Nakayama, Shinsuke; Iwamoto, Osamu; Watanabe, Yukinobu*; Ogata, Kazuyuki*
no journal, ,
Intensive neutron sources using deuteron accelerators have been proposed for various applications such as irradiation testing of fusion reactor materials and production of medical radioisotopes. To contribute to the design study of such neutron sources, a deuteron reaction data file for light nuclei (Li-6,7, Be-9, C-12,13), JENDL/DEU-2020 was developed. In addition, the validation of it by the simulation with the codes such as PHITS was performed. As a result, the simulation based on JENDL/DEU-2020 reproduced the measured thick-target neutron yields better than those with the reaction models implemented in PHITS.
Nakagawa, Naoki*; Fujimoto, Nozomu*; Ho, H. Q.; Hamamoto, Shimpei; Nagasumi, Satoru; Ishitsuka, Etsuo
no journal, ,
no abstracts in English
Ikeda, Reiji*; Ho, H. Q.; Fujimoto, Nozomu*; Hamamoto, Shimpei; Nagasumi, Satoru; Ishitsuka, Etsuo
no journal, ,
no abstracts in English
Sato, Kazuyuki; Endo, Yuya; Maeda, Tsuyoshi; Uezu, Yasuhiro; Lochard, J.*; Clement, C.*; Fujita, Hiroki*; Ando, Ryoko*
no journal, ,
no abstracts in English
Kanari, Yukiko; Uezu, Yasuhiro
no journal, ,
no abstracts in English
Endo, Shunsuke; Kimura, Atsushi; Nakamura, Shoji; Iwamoto, Osamu; Iwamoto, Nobuyuki; Toh, Yosuke; Segawa, Mariko; Maeda, Makoto; Tsuneyama, Masayuki*
no journal, ,
no abstracts in English
Hosokawa, Tomoaki*; Fujiwara, Hideki*; Kamoshida, Shuichi*; Anzai, Kiyoshi*; Nakano, Masanao; Koike, Yuko; Yamada, Ryohei; Nagaoka, Mika
no journal, ,
no abstracts in English
Nakano, Masanao; Koike, Yuko; Yamada, Ryohei; Nagaoka, Mika; Hosokawa, Tomoaki*; Fujiwara, Hideki*; Kamoshida, Shuichi*; Anzai, Kiyoshi*
no journal, ,
no abstracts in English
Watanabe, Nao; Sugawara, Takanori; Nishihara, Kenji
no journal, ,
In order to design an accelerator driven system (ADS), a beam window, which divides between areas of an accelerator and a subcritical core, is one of important structures. JAEA made a 3D model of a beam window and surrounding lead bismuth thermal flow field and developed a coupled analysis system of thermal hydraulics and structure in ANSYS Workbench. In the system a heat generation distribution from PHITS code is read, and steady thermal hydraulic of LBE coolant and stress of the beam window are calculated by Fluent code. Then its eigenvalue buckling is evaluated. In 3D analyses, non-axisymmetric evaluations are considered and radial deformations are found in low buckling modes.
Tada, Kenichi; Ikehara, Tadashi; Ono, Michitaka*; Tojo, Masayuki*
no journal, ,
Comparison of the nuclear data processing code is realised using nuclear data processing code FRENDY which has been developed in JAEA. In this study, we compared the difference of the nuclear data processing codes between FRENDY and NJOY. The impact of difference between open nuclear data processing codes on neutron transport calculations were also investigated. In this presentation, the difference of the nuclear data processing method between FRENDY and NJOY and ACE verification project carried out by IAEA.
Ono, Michitaka*; Tojo, Masayuki*; Tada, Kenichi; Ikehara, Tadashi
no journal, ,
The difference of the nuclear data processing affects the difference of cross section library and neutronics calculation. This presentation explains the comparisons of the cross section libraries and neutronics calculation results.
Nakayama, Hiromasa; Satoh, Daiki; Furuta, Yoshihiro; Nagai, Haruyasu
no journal, ,
We have been developing a method for estimating radionuclide concentration distributions in the atmosphere and release amount by combining atmospheric dispersion simulations with radiation measuring. This method has high potential to improve reliability of the simulation accuracy by incorporating the obtained release amount and concentration distributions near a source point into atmospheric dispersion simulations. Because there are no real data on radionuclide concentrations, we have a plan to calculate the test data on radionuclide concentration distributions in the atmosphere by computational simulation and validate the estimation method. In this study, we report the method for calculating them used for the test data.
Kataoka, Shoji; Matsushima, Ryotatsu; Sato, Fuminori; Terunuma, Tomomi
no journal, ,
The Low-Level Radioactive Waste Treatment Technology Development Facility (LWTF) of Tokai Reprocessing Facility has been constructed as a facility for processing low radioactive liquid waste and solid waste generated from the reprocessing facility, and cold tests are being conducted. In this facility, the nitrate waste liquid generated by the treatment of liquid waste was decided to be solidified using borate, but now it is planned to replace it with carbonate waste liquid and then make it cement solid. Therefore, we are proceeding with examination and design for the introduction of equipment. In this report, we conduct a cement kneading and solidification test on a carbonate waste liquid on a real scale (200L drum), and report on the results of examining the influence of the cement solidified body over time and the strength when the waste liquid composition changes.
Nagai, Takayuki; Okamoto, Yoshihiro; Kaneko, Koji; Motokawa, Ryuhei; Kobayashi, Hiromi*; Homma, Masanobu*; Hirono, Kazuya*
no journal, ,
To understand the structural property of borosilicate glass frit for vitrification of radioactive wastes, we prepared the glass frit samples which coordinated alkaline component and B
O
amount and measured the Si-O bridge structure of those samples by using Raman spectrometer. Moreover, we made the simulated waste glass samples which added non-radioactive nitrate solution to those frit and observed a change of Raman spectra by glass composition.
Mishima, Ria; Tachioka, Sotaro*; Inaba, Yusuke*; Harigai, Miki*; Matsumura, Tatsuro; Watanabe, Shinta*; Onoe, Jun*; Nakase, Masahiko*; Takeshita, Kenji*
no journal, ,
In Japan, the final disposal of high level liquid waste (HLLW) will be done after vitrification into borosilicate glass and then disposed into deep underground. In this vitrification process, there are some concerns. The first concern is precipitation of platinum group metals (PGMs) in the melter due to their low solubility into borosilicate glass. The second concern is the formation of yellow phase caused by Mo content. The final concern is the generation of huge number of vitrified glasses and the requirement of wide space needed for final disposal. Among many kinds of extractants and adsorbents for separation of such metal ions, metal hexacyanoferrate (HCFs) were reported to have an ability to adsorb PGMs. The objective of this study is to elucidate the adsorption behavior of aluminum hexacyanoferrate (AlHCF) for various metal ions and understand the relation between elution and adsorption. The effect of synthetic and workup conditions on PGM and Mo adsorption from simulated HLLW (sHLLW) was surveyed. Also, the relationship between adsorption of metal ions and elution of the AlHCF was studied. The synthesized AlHCF showed adsorption performance for PGMs and Mo in simulated HLLW. As a result of an adsorption test with a Pd single component solution to investigate the adsorption mechanism, the eluted element ratio was Fe:Al = 1:4 in the Pd adsorption test. However, the element ratio was Fe:Al = 3:4 in the original AlHCF. Therefore, it was suggested the existence of not only Pd adsorption, but also resorption and stabilization mechanisms.