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Oral presentation

Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors, 25; Project overview and progress until 2020

Yamano, Hidemasa; Takai, Toshihide; Emura, Yuki; Higashi, Hideo*; Fukuyama, Hiroyuki*; Nishi, Tsuyoshi*; Ota, Hiromichi*; Morita, Koji*; Nakamura, Kinya*; Fukai, Hirofumi*; et al.

no journal, , 

A research project has been conducting thermophysical property measurement of a eutectic melt, eutectic melting experiments and material analysis, physical model development for the eutectic melting reaction, and reactor application analysis in order to simulate the eutectic melting reaction and relocation behavior of boron carbide as a control rod material and stainless steel during a core disruptive accident in an advanced sodium-cooled fast reactor designed in Japan. This paper describes the project overview and progress until JFY2020.

Oral presentation

Investigation on distribution of radioactive substances in Fukushima, 7; Estimation of exposed dose by measurement of air dose rate

Sato, Rina; Yoshimura, Kazuya; Sanada, Yukihisa; Sato, Tetsuro*; Takagi, Marie*

no journal, , 

no abstracts in English

Oral presentation

Development of failure mitigation technologies for improving resilience of nuclear structures, 11; Analysis for enhancing resilience of next-generation nuclear power plants

Futagami, Satoshi; Ando, Masanori; Yamano, Hidemasa

no journal, , 

To enhance resilience of next-generation nuclear power plants, the authors have performed a three-dimensional analysis of structures with an earthquake-resistant lower support structure, assuming a protected loss of heat sink event, which may cause all decay heat removal systems to lose their functions immediately after reactor shutdown. The results show how the reactor vessel and guard vessel deform at extremely high temperatures.

Oral presentation

Measurement and calculation analysis of shielding material's performance for MOX containing americium

Okada, Toyofumi; Shibanuma, Tomohiro; Honda, Fumiya; Komeno, Akira; Kikuno, Hiroshi

no journal, , 

$$^{241}$$Am is generated by beta-decay of $$^{241}$$Pu. In the case of treating MOX, it is important for shielding about 60keV gamma-ray emitted by $$^{241}$$Am. Also getting dose rate data of MOX containing $$^{241}$$Am is valuable. In this work, we measured gamma-ray dose rate from MOX containing $$^{241}$$Am by changing thickness of shielding materials and range between MOX and measuring instruments. Also we confirmed that calculating analysis is useful for evaluation of shielding material's performance.

Oral presentation

Development of failure mitigation technologies for improving resilience of nuclear structures, 6; How to consider the effects of fracture control into resilience index

Demachi, Kazuyuki*; Kuwabara, Yuto*; Chen, S.*; Kasahara, Naoto*; Nishino, Hiroyuki; Onoda, Yuichi; Kurisaka, Kenichi

no journal, , 

no abstracts in English

Oral presentation

Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors, 26; Density and surface tension of 15mass% B$$_{4}$$C-SS eutectic molten materials

Fukuyama, Hiroyuki*; Higashi, Hideo*; Yamano, Hidemasa

no journal, , 

The purpose of this study is to develop the thermophysical property model needed to simulate the behavior of the eutectic compound of the control rod material (boron carbide (B$$_{4}$$C)) and the structural material of a reactor vessel (stainless steel: SUS316L (SS)) during a core disruptive accident in a sodium-cooled fast reactor. This paper describes the liquidus temperature, density and surface tension of the molten compound of 15mass% B$$_{4}$$C-SS systematically measured with the High-Temperature Thermophysical Property Measurement System (PROSPECT).

Oral presentation

Measurement test of non-destructive assay for quantification of nuclear materials in fuel debris, 3; Determination of impurity in nuclear materials by using gamma-ray spectroscopy

Suzuki, Risa; Nomi, Takayoshi; Nagatani, Taketeru; Shiromo, Hideo; Shiba, Tomooki; Kaburagi, Masaaki; Okumura, Keisuke; Kosuge, Yoshihiro*; Takada, Akira*; Nauchi, Yasushi*

no journal, , 

no abstracts in English

Oral presentation

Criticality analysis of inverse power law random media with spectral range control

Ueki, Taro

no journal, , 

In the power spectrum measurement of natural and engineering phenomena, there are upper and lower limits in the frequency domain variables. Therefore, in this excerpt, we report that the randomized Weierstrass function for the modelling of inverse power law spectrum has been extended so that the range of frequency domain variable can be set arbitrarily. This extension is born out of breaking the relationship with the convergence issue in the fractalness of Weierstrass function and thus named an incomplete randomized Weierstrass function (IRWF). An example of the uncertainty evaluation of neutron effective multiplication factor using IRWF is shown for fuel debris in a sufficiently water-moderated environment.

Oral presentation

Analysis of alpha radionuclide in the contaminated water at the torus room of unit #2 reactor of Fukushima Daiichi NPS, 2; Analysis of alpha-emitting nuclides of solid components by ICP-MS

Ouchi, Kazuki; Yomogida, Takumi; Oka, Toshitaka; Kitatsuji, Yoshihiro; Koma, Yoshikazu; Konno, Katsuhiro*

no journal, , 

In order to grasp the existence state of $$alpha$$-nuclides contained as particulate solids in the contaminated water, $$alpha$$-nuclide concentrations in the solids and the filtrate which classified according to particle size using filters with pore sizes of 10, 1, 0.1 and 0.02 $$mu$$m were quantitatively analyzed by ICP-MS. Reactor-derived U was detected in the particulate solids in the contaminated water, and most of them settled deeply as coarse particles of $$>$$10 $$mu$$m. U existing in the water as fine particles and ions was also confirmed.

Oral presentation

Analysis of alpha radionuclide in the contaminated water at the torus room of unit #2 reactor of Fukushima Daiichi NPS, 4; Detection of fine particle containing $$alpha$$-emitters by SEM-EDX and alpha track

Yomogida, Takumi; Ouchi, Kazuki; Oka, Toshitaka; Kitatsuji, Yoshihiro; Koma, Yoshikazu; Konno, Katsuhiro*

no journal, , 

It has been revealed from the analysis results of ICP-MS and $$alpha$$-ray spectrometry that the contaminated water at the torus room of Unit 2 reactor contains $$alpha$$-nuclides which were derived from nuclear fuels. To investigate the morphology of these $$alpha$$-nuclides, we tried to detect particles containing $$alpha$$-nuclides by scanning electron microscopy-X-ray detection (SEM-EDX) and the alpha track method. As a result of SEM-EDX observation, several sub-$$mu$$m to several $$mu$$m size particles containing U were identified. These particles contain elements derived from fuel cladding materials such as Zr, suggesting the possibility that these particles are fine fuel debris. The particles containing alpha emitters were identified by alpha-track method. These particles with few hundred $$mu$$m in diameter were mainly composed of iron oxide, which suggest Pu, Am, Cm were attached to the surface of these particles. These results indicated that the forms of U and other $$alpha$$-nuclides were different.

Oral presentation

Oral presentation

Interference removal for high-sensitivity rapid analysis of $$^{107}$$Pd in radioactive rubbles by ICP-MS/MS

Iwahashi, Hiroyuki; Do, V. K.; Furuse, Takahiro; Ota, Yuki; Homma, Shunta; Kurosawa, Kiyoko*; Motoki, Yoshiaki*; Hirosawa, Takashi

no journal, , 

The radiometric determination of beta emitting $$^{107}$$Pd (half-life of 6.5 million years) requires a multiple-step chemical separation and a time-consuming radioactive measurement. Inductively coupled plasma tandem mass spectrometry (ICP-MS/MS) with recent technological advances in interference removal by two quadrupole mass filters and a collision/reaction cell could be an alternative for highly sensitive analysis of long-lived radionuclides. In this study, we have developed an analytical method for the determination of $$^{107}$$Pd in concrete rubble by ICP-MS/MS combined with single-column chromatographic separation. A simplified procedure for the separation of Pd from concrete matrices was developed. The measurement condition was optimized to completely suppress the interference including the isobar $$^{107}$$Ag and the sample matrices. The application of the developed method to radioactive concrete rubble is under consideration.

Oral presentation

Analysis of alpha radionuclide in the contaminated water at the torus room of unit #2 reactor of Fukushima Daiichi NPS, 1; Outline of the state analysis of alpha radionuclides containing in the solid component

Kitatsuji, Yoshihiro; Ouchi, Kazuki; Yomogida, Takumi; Oka, Toshitaka; Nitta, Ayako; Hinai, Hiroshi; Koma, Yoshikazu; Konno, Katsuhiro*

no journal, , 

In order to clarify the chemical species of alpha nuclides in the contaminated water of the Fukushima Daiichi Nuclear Power Station, sludge was classified by particle size. The concentration of alpha radioisotope was measured and the particles were investigated. Most alpha particles were larger than 10 micrometers and settled at the bottom of the torus chamber.

Oral presentation

Investigation on distribution of radioactive substances in Fukushima, 20; Comparison of dose rate dynamic models between UNSCEAR 2020 and JAEA 2017

Kinase, Sakae; Mikami, Satoshi; Ando, Masaki; Saito, Kimiaki

no journal, , 

no abstracts in English

Oral presentation

Solubility of palladium in the presence of $$alpha$$-isosaccharinic acid, 2

Iwata, Hajime; Kimuro, Shingo; Kitamura, Akira; Miyabe, Shunsuke*; Maeno, Mamiko*; Tanaka, Takeru*; Hieda, Manami*

no journal, , 

The effect of $$alpha$$-isosaccharinic acid (ISA) on the solubility of palladium (Pd) in alkaline aqueous solution (pH 8.5, 10.0) was investigated by solubility experiments. The Pd concentration increased with the increase of ISA concentration. The equilibrium constant was calculated from the solubility data obtained in this study.

Oral presentation

Experiments of bentonite spraying method for the clay plug, 1; Investigation of sprayed bentonite properties

Kimura, Shun; Takeda, Masaki; Motoshima, Takayuki*; Dan, Hanae*

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Diffusion behavior of iodide and cesium ions in hardened cement paste

Kawato, Takaya*; Ishida, Keisuke*; Yamamoto, Takeshi*; Minato, Daisuke*; Fujisaki, Kiyoshi*; Hamamoto, Takafumi*; Mihara, Morihiro

no journal, , 

no abstracts in English

Oral presentation

Aerial radiation monitoring via manned helicopter around nuclear facilities

Futemma, Akira; Kudo, Tamotsu

no journal, , 

During a nuclear emergency, aerial radiation monitoring (ARM) via manned helicopters could be utilized as a way of radiation measurement. Natural background radiation maps surrounding twelve nuclear facilities in Japan are developed by ARM to contribute to make an appropriate evaluation of the environmental radiological effect during a nuclear emergency.

197 (Records 1-20 displayed on this page)