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Oral presentation

Theoretical model analysis of charged-particle emission spectra from the $$^{12}$$C+p reaction

Nakayama, Shinsuke; Watanabe, Yukinobu*

no journal, , 

In the effect assessment on healthy cells in particle therapy, the charged particle emission spectra from nuclear reactions on light element (e.g., C, N, O) constituting a living body are important as fundamental data. Unlike medium-heavy nuclei, nuclear reactions on light nuclei can cause particle emission from a discrete state of residual nuclei. The effect of this emission process on the spectra is analyzed using the nuclear reaction code CCONE, taking the $$^{12}$$C+p reaction as an example. As a result, the reproducibility the experimental proton and alpha-particle emission spectra is largely improved by considering particle emission from discrete states of residual nuclei. This result indicates that it is important to consider particle emission from discrete states of residual nuclei in the calculation of particle emission spectra from nuclear reactions on light nuclei.

Oral presentation

Neutron capture cross section measurement of $$^{129}$$I and $$^{127}$$I using ANNRI at MLF/J-PARC

Rovira Leveroni, G.; Kimura, Atsushi; Nakamura, Shoji; Endo, Shunsuke; Iwamoto, Osamu; Iwamoto, Nobuyuki; Toh, Yosuke; Segawa, Mariko; Maeda, Makoto; Katabuchi, Tatsuya*

no journal, , 

Oral presentation

Development of numerical simulation method to evaluate heat transfer of fuel debris in air cooling, 5; Preliminary analysis of thermal behavior in PCV

Uesawa, Shinichiro; Ono, Ayako; Yamashita, Susumu; Yoshida, Hiroyuki

no journal, , 

To evaluate the thermal behavior of fuel debris in PCVs of TEPCO's Fukushima Daiichi Nuclear Power Station for air cooling, JAEA has developed a numerical simulation method with JUPITER. The previous work reported JUPITER with a porous medium model was capable to calculate thermal behavior of a porous medium. In this report, we report the result of the preliminary numerical analysis of thermal behavior in the PCV of Fukushima Daiichi Nuclear Power Station Unit 2. The numerical result showed air in the RPV and the pedestal was heated with fuel debris, and natural convection was generated. Therefore, the numerical simulation method is expected to evaluate the thermal behavior in the PCV for air cooling.

Oral presentation

Investigation on separation and extraction behavior of An and Ln using hydrophilic and lipophilic multidentate ligands

Sasaki, Yuji; Kaneko, Masashi; Ban, Yasutoshi

no journal, , 

Using TODGA and ADAAM, which are developed by JAEA, the recovery of total amounts of An and Ln, and mutual separation of Am/Cm have been achieved. Recent studies give the very high SF(An/Ln) over 100 and show the different chemical behavior between An and Ln, using solvent extraction of tri, tetradentate extractant and masking agent. We confirm these conditions to satisfy the subsequent ones, to maintain the suitable concentrations of extractants and masking agents for Ln recovery, and to show high SF using sets of D values over and under 1. In the presentation, we will show the difficulties of An/Ln separation and direction of researches, and present the SF(An/Ln) using various extractants and masking agents.

Oral presentation

Development of advanced neutronics/thermal-hydraulics coupling simulation system, 9; Development of measurement method for gas-liquid two-phase flow inside a fuel bundle to obtain code validation data

Ono, Ayako; Okamoto, Kaoru*; Makino, Yasushi*; Hosokawa, Shigeo*; Yoshida, Hiroyuki

no journal, , 

JAEA has been developing an advanced neutronic/thermal-hydraulics coupling simulation system. In the system, the detailed thermal-hydraulics codes JUPITER and TPFIT, which are based on an interface-capturing method, will be adopted to simulate thermal-hydraulics in a fuel bundle. The experimental data and findings relating to the two-phase flow in a fuel bundle are needed to validate JUPITER and TPFIT. In this study, we propose a new measurement method to measure the bubbly flow in a narrow channel, such as a subchannel, by combining laser-doppler velocimetry and photodiodes. The proposed measurement method is cross-checked by a conductance probe and is confirmed for its validity.

Oral presentation

Development of measurement method for an absolute value of resonance energy

Endo, Shunsuke; Kawamura, Shiori*; Tsuchikawa, Yusuke; Mishima, Kenji*; Kimura, Atsushi; Nakamura, Shoji; Iwamoto, Osamu; Iwamoto, Nobuyuki; Rovira Leveroni, G.

no journal, , 

no abstracts in English

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 41; Determination of degradation acceleration on solidified body by efflorescence test

Sato, Junya; Kuramochi, Ryo*; Shimizu, Koki; Matsumoto, Saori; Taniguchi, Takumi; Kuroki, Ryoichiro; Osugi, Takeshi

no journal, , 

no abstracts in English

Oral presentation

Development of measurement method for methane gas generation volume due to decomposition of combustible materials disposed of in trench disposal facilities

Nakamura, Mizuki; Sato, Junya; Nakata, Hisakazu; Sakai, Akihiro; Osugi, Takeshi

no journal, , 

no abstracts in English

Oral presentation

Phase 2 of Monju decommissioning, 1; Overall picture of Monju decommissioning plan and positioning of Phase 2

Naruse, Keiji; Matsui, Kazuaki; Obata, Ikuhito; Sawazaki, Hiromasa; Goto, Takehiro; Jo, Takahisa

no journal, , 

no abstracts in English

Oral presentation

Reducing the risk of possessing sodium for Monju

Nishino, Yuki; Kuramoto, Shimpei; Naruse, Keiji; Nishino, Hajime; Goto, Takehiro; Takeuchi, Toru

no journal, , 

no abstracts in English

Oral presentation

Investigation on distribution of radioactive substances in Fukushima, 5; Comparison of dose evaluation calculations for bremsstrahlung photons caused by high energy $$beta$$ rays using PHITS and GEANT4 codes

Shikaze, Yoshiaki

no journal, , 

Among the radioactive nuclides emitted inside the nuclear reactor buildings by the Fukushima Daiichi nuclear reactor accident, high-energy beta-ray sources such as strontium-90 and yttrium-90 generate bremsstrahlung photons in the materials which constitute wall, floor and interior structure of the building. Therefore, evaluation of the bremsstrahlung radiation dose to the workers in the nuclear reactor building is important for radiation exposure management. To investigate calculation precision of the bremsstrahlung dose evaluation, the results of PHITS and GEANT4 codes were compared. In the calculation, behind various shielding plates the water cylinder was set, and the deposited energy spectrum and absorbed dose in the water cylinder by the bremsstrahlung were compared in this presentation.

Oral presentation

Phase 2 of Monju decommissioning, 3; Process approaches and assessment of residual sodium for sodium equipment disassembling

Isobe, Yuta; Hayashi, Takehiro; Tanigaki, Takanori; Miyoshi, Nobuaki; Kawanago, Sho; Obata, Ikuhito; Kobayashi, Takanori

no journal, , 

no abstracts in English

Oral presentation

Anthropogenic impacts on temporal decrease in air dose rate in urban areas, 2; Simulation analysis using detailed environmental model by 3D-ADRES

Kim, M.; Yoshimura, Kazuya; Sakuma, Kazuyuki; Malins, A.*; Abe, Tomohisa; Nakama, Shigeo; Machida, Masahiko; Saito, Kimiaki

no journal, , 

The dynamics of radiocesium differs depending on the ground surface coverage, and a detailed environmental model was created and Monte Carlo simulation analysis was conducted to quantitatively evaluate the effects of these differences on the reduction of air dose rates in urban areas. As a result, it was confirmed that the presence of human activities in urban areas promotes the decay of air dose rates.

Oral presentation

Evaluation of nuclear data for the next JENDL, 1; Neutron nuclear data on Mo isotopes

Iwamoto, Nobuyuki

no journal, , 

no abstracts in English

Oral presentation

Development of nondestructive measurement technique for nuclear materials using fast fission

Maeda, Makoto; Komeda, Masao; Toh, Yosuke

no journal, , 

no abstracts in English

Oral presentation

Impact of $$^{9}$$Be thermal scattering law data considering crystallite size, 1; Critical experiment analysis

Konno, Chikara

no journal, , 

Recently European Spallation Source group reported that the thermal scattering law data of $$^{9}$$Be changed with the crystallite size of beryllium. We calculated the effective multiplication factor for the critical experiment MIX-MET-FAST-007 with JENDL-5 and the ESS thermal scattering law data of $$^{9}$$Be. The calculation results indicated that the effective multiplication factor decreased as the crystallite size of beryllium increased in the cases where the beryllium reflector was thicker than 16 cm.

Oral presentation

R&D on medical RI production using domestic nuclear infrastructures to achieve self-preparedness (2), 6; Ac purification and Ra reuse processes in Ac-225 production using fast reactor

Ouchi, Kazuki; Kitatsuji, Yoshihiro; Maeda, Shigetaka; Takaki, Naoyuki*

no journal, , 

In previous study, we have studied the purification process for efficient recovery of Ac-225 produced by neutron irradiation of Ra-226 in a fast reactor. In this presentation, the reuse process for re-irradiating Ra-226 after separation of Ac-225 was studied by using Ba and La as alternative elements. By using Ln resin as adsorbent and changing the nitric acid concentration, the conditions under which Ra can be isolated from impurities expected to be produced by irradiation were clarified. We propose a purification process for Ac using DGA resin and a recycling process for Ra using Ln resin.

Oral presentation

R&D on medical RI production using domestic nuclear infrastructures to achieve self-preparedness (2), 6; RI production using the experimental fast reactor Joyo

Sasaki, Yuto; Sano, Aaru; Itagaki, Wataru; Maeda, Shigetaka; Takaki, Naoyuki*

no journal, , 

no abstracts in English

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 37; Investigation of solidification range for simulated sludge

Taniguchi, Takumi; Kuramochi, Ryo*; Sakamoto, Ryo*; Osawa, Norihisa*; Kaneda, Yoshihisa*; Matsuzawa, Kazuki*; Yamamoto, Takeshi*; Kuroki, Ryoichiro; Osugi, Takeshi

no journal, , 

no abstracts in English

206 (Records 1-20 displayed on this page)