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Oral presentation

Development of a fast response neutron detector bank for fast neutron direct interrogation method

Maeda, Makoto; Furutaka, Kazuyoshi; Ozu, Akira; Komeda, Masao; Toh, Yosuke

no journal, , 

no abstracts in English

Oral presentation

Study on accuracy improvement of fast-neutron capture reaction data of long-lived MA for development of nuclear transmutation systems, 4; Development of MA nuclear data evaluation method

Iwamoto, Nobuyuki; Iwamoto, Osamu; Nakamura, Shoji; Kimura, Atsushi; Katabuchi, Tatsuya*; Rovira Leveroni, G.*

no journal, , 

no abstracts in English

Oral presentation

Study on accuracy improvement of fast-neutron capture reaction data of long-lived MA for development of nuclear transmutation systems, 2; Development of a neutron beam filter system and capture cross section measurement at ANNRI in J-PARC

Kimura, Atsushi; Nakamura, Shoji; Iwamoto, Nobuyuki; Iwamoto, Osamu; Katabuchi, Tatsuya*; Terada, Kazushi*; Rovira, G.*; Hori, Junichi*; Shibahara, Yuji*

no journal, , 

no abstracts in English

Oral presentation

Measuring isotopic abundance using nuclear resonance fluorescence

Omer, M.; Shizuma, Toshiyuki*; Hajima, Ryoichi*; Koizumi, Mitsuo

no journal, , 

Oral presentation

Reduction and resource recycling of high-level radioactive wastes through nuclear transmutation, 5-1; Development of nuclear data library JENDL/ImPACT-2018 for nuclear transmutation of LLFP

Iwamoto, Osamu; Kunieda, Satoshi; Furutachi, Naoya*; Minato, Futoshi; Iwamoto, Nobuyuki; Nakayama, Shinsuke; Ebata, Shuichiro*; Nishihara, Kenji; Yoshida, Toru*; Watanabe, Yukinobu*; et al.

no journal, , 

Treatment of high-level radioactive wastes produced by reactor operation is are very important problem for nuclear energy. A new nuclear data library JENDL/ImPACT-2018 has been developed as a part of the ImPACT project aiming at reduction and resource recycling of LLFPs through nuclear transmutation. Due to possible creation of a lot of secondary products including unstable nuclei, the nuclear reaction data have been evaluated with improving predictability of theoretical calculations.

Oral presentation

PHITS models for ambient dose equivalent rates in Fukushima's Radiocesium contaminated forests

Malins, A.; Imamura, Naohiro*; Niizato, Tadafumi; Kim, M.; Sakuma, Kazuyuki; Shinomiya, Yoshiki*; Miura, Satoru*; Machida, Masahiko

no journal, , 

Oral presentation

Implementation of random sampling for ACE-format cross sections using FRENDY

Kondo, Ryoichi*; Endo, Tomohiro*; Yamamoto, Akio*; Tada, Kenichi

no journal, , 

The random sampling module for ACE format cross sections are developed using modules of FRENDY. This module perturbs the cross sections and other parameters in ACE format cross section library using covariance data. The GODIVA reactor is used and the calculation results of TSUNAMI-1D are compared to verify this module.

Oral presentation

Cs chemisorption behavior onto stainless steel during LWR severe accident, 2; Property change of Cs-chemisorbed deposit by temperature increase

Nishioka, Shunichiro; Takase, Gaku; Nakajima, Kunihisa; Suzuki, Eriko; Osaka, Masahiko

no journal, , 

The chemical/physical properties of Cs-chemisorbed deposit could change along with the progression of LWR severe accident (SA). In this study, the influence of temperature change on the properties of Cs-chemisorbed deposit was investigated experimentally. It was found that Cs-Fe-O compounds, which had been formed by chemisorption at 873 K, could transform into Cs-Si-(Fe)-O compounds at 1273 K.

Oral presentation

Microscopic structure of organic phase during solvent extraction and elucidation of third-phase formation mechanism

Motokawa, Ryuhei; Kobayashi, Toru; Endo, Hitoshi

no journal, , 

no abstracts in English

Oral presentation

Development of a scalable and deformable stylized eye model for radiation dose assessment

Furuta, Takuya; El Basha, D.*; Iyer, S. S. R.*; Correa Alfonso, C. M.*; Bolch, W. E.*

no journal, , 

With recent changes in the recommended annual dose limit on eye lens by International Commission on Radiological Protection, several Monte Carlo studies has been performed using a computational eye model. Although there are a large variety in size and shape for individual eyes, the eye model of one standard eye size and shape was adopted in most of those studies. We therefore constructed a geometric eye model that is both scalable and deformable, and studied dosimetry influence on the variation of the eye size and shape in the standard radiation geometries using Monte Carlo radiation transport code PHITS. We confirmed that only a trivial dependence on the eye size and shape, namely variation of the depth location of the ocular structures, was observed for radiation exposure in the broad radiation geometries.

Oral presentation

Temporal variation of atmospheric radioactive cesium and the variation trend

Abe, Tomohisa; Yoshimura, Kazuya; Sanada, Yukihisa

no journal, , 

In this study, we analyzed the variation trend of cesium concentration in the atmosphere using a data set that the Nuclear Regulation Authority regular measured the atmospheric radioactivity after the Fukushima Nuclear Plant Accident. In addition, we calculated re-suspension factor in Fukushima using the initial fallout map of cesium by the third airborne monitoring survey.

Oral presentation

Development of analytical methods for metal elements in reprocessing solution by optical emission spectrometry based on liquid electrode plasma, 5; Determination of alkaline and alkaline earth metals in reprocessing process solution

Yamamoto, Masahiko; Do, V. K.; Taguchi, Shigeo; Takamura, Yuzuru*; Kuno, Takehiko

no journal, , 

The measurement conditions of Na, K, Ca, Sr, Ba by liquid electrode plasma optical emission spectrometry (LEP-OES) have been optimized. The samples from reprocessing process plant such as highly active liquid waste has been also measured by LEP-OES.

Oral presentation

Model extension of probabilistically disordered media and its implementation in solomon code

Ueki, Taro

no journal, , 

The randomized Weierstrass function (RWF) is a useful tool for the uncertainty evaluation of the criticality of disordered media. This excerpt reports the extension of RWF methodology covering a wide range of power law spectra in order to simulate various disordered mixtures of materials. The extended RWF is then demonstrated using the Monte Carlo Solver Solomon.

Oral presentation

Investigation of impact of ladder numbers on probability table

Tada, Kenichi

no journal, , 

The ladder number has large impact on the probability table generation time. In this paper, we investigate the appropriate ladder number to generate probability table. The calculation results indicate that the appropriate ladder number to generate probability table is 100.

Oral presentation

Behavior of high-burnup advanced fuels under reactivity-initiated accident (RIA) and loss-of-coolant accident (LOCA), 6; High temperature oxidation behavior of high-burnup advanced cladding tubes

Kakiuchi, Kazuo; Narukawa, Takafumi; Obata, Hiroki; Amaya, Masaki

no journal, , 

JAEA has conducted studies on fuel behaviors during loss-of-coolant-accidents (LOCA) using high-burnup advanced fuel cladding tubes. We report the evaluation results on the effects of the burnup extension and the change in the alloy compositions on high temperature oxidation of high-burnup advanced fuel cladding.

Oral presentation

Behavior of high-burnup advanced fuels under reactivity-initiated accident (RIA) and loss-of-coolant accident (LOCA), 1; Outline

Amaya, Masaki; Ito, Masatoshi; Komuro, Kazuma

no journal, , 

no abstracts in English

Oral presentation

Study on accuracy improvement of fast-neutron capture reaction data of long-lived MA for development of nuclear transmutation systems, 1; Project overview

Katabuchi, Tatsuya*; Iwamoto, Osamu; Hori, Junichi*; Iwamoto, Nobuyuki; Kimura, Atsushi; Nakamura, Shoji; Shibahara, Yuji*; Terada, Kazushi*; Takamiya, Koichi*; Fukutani, Satoshi*; et al.

no journal, , 

Accurate neutron capture cross sections on long-lived MA at fast region are required for developments of nuclear transmutation system. A study to improve accuracy of the fast neutron capture cross sections has been started as a collaborative project among Tokyo Institute of Technology, Japan Atomic Energy Agency and Kyoto University since 2017. This talk reports about the background, the object and the total plan of the project as the first one of the series presentations.

Oral presentation

Construction of CHART of the nuclides 2018

Koura, Hiroyuki; Katakura, Junichi*; Tachibana, Takahiro*; Minato, Futoshi

no journal, , 

no abstracts in English

Oral presentation

Study on accuracy improvement of fast-neutron capture reaction data of long-lived MA for development of nuclear transmutation systems, 3; Development of impurity and isotope assay technique of samples

Shibahara, Yuji*; Hori, Junichi*; Fukutani, Satoshi*; Takamiya, Koichi*; Katabuchi, Tatsuya*; Terada, Kazushi*; Iwamoto, Osamu; Iwamoto, Nobuyuki; Kimura, Atsushi; Nakamura, Shoji

no journal, , 

As a part of the Nuclear System Research and Development Project "Study on accuracy improvement of fast-neutron capture reaction data of long-lived MA for development of nuclear transmutation systems", developments of the technology mainly using the mass spectroscopy method for the isotope and impurity analysis in samples. This presentation reports status of the study on the analysis technology with the surface ionization type mass spectroscopy device.

174 (Records 1-20 displayed on this page)