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Oral presentation

Fault reactivation experiment and frictional properties of Mont Terri Rock Laboratory, Switzerland

Aoki, Kazuhiro; Seshimo, Kazuyoshi; Nussbaum, C.*; Guglielmi, Y.*; Shimamoto, Toshihiko*; Sakai, Toru*; Kametaka, Masao*; Ma, S.*; Yao, L.*

no journal, , 

In order to contribute to the Fault Slip experiment, JAEA has performed friction experiment of borehole cores of the measured interval using a rotary-shear low to high-velocity friction apparatus at Institute of Geology, China Earthquake Administration. Friction experiments were done either dry with room humidity or with 30wt% of H$$_{2}$$O, at a normal stress of 1.4 and 4.0 MPa and at low to intermediate slip rates ranging 0.21 microns/s to 2.1mm/s. Cylindrical specimens of Ti-Al-V alloy with 40 mm in diameter were used as rotary and stationary pistons and the alloy pistons exhibit similar behaviors as host rock specimens.

Oral presentation

Development of an optimization analysis sequence OPAS and its application to the prediction models for radioactive cesium distribution

Suzuki, Tadakazu*; Sugita, Takeshi*; Kinase, Sakae; Kurikami, Hiroshi; Kitamura, Akihiro

no journal, , 

An optimization analysis sequence OPAS was developed and applied to prediction models for radioactive cesium distribution. The method and results will be presented.

Oral presentation

Investigation of the impact of the difference of probability table calculation method

Tada, Kenichi

no journal, , 

JAEA started to develop the new nuclear data processing system FRENDY. FRENDY can generate the ACE (A Compact ENDF) file without NJOY module and it is implemented not only NJOY's nuclear data processing method but also FRENDY original method. In this presentation, the impact of the difference of nuclear data processing method on the k-effective value is investigated.

Oral presentation

R&D of differential die-away system for nuclear non-proliferation and nuclear security

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

no journal, , 

no abstracts in English

Oral presentation

Development of solidification techniques with minimised water content for secondary radioactive aqueous wastes in Fukushima, 5; Leaching rate of Sr$$^{2+}$$ and Cl$$^{-}$$

Irisawa, Keita; Taniguchi, Takumi; Namiki, Masahiro*; Garc$'i$a-Lodeiro, I.*; Osugi, Takeshi; Nakazawa, Osamu; Kinoshita, Hajime*

no journal, , 

no abstracts in English

Oral presentation

A Correction to the non-resonant process in the R-matrix analysis

Kunieda, Satoshi

no journal, , 

We propose a new method for the non-resonant process in the R-matrix theory, which is associated with additional background poles exclusive to the incident particles. This method is applied to the simultaneous analysis of the $$^6$$Li(p,p$$_0$$) $$^6$$Li, $$^6$$Li(p,$$alpha_0$$) $$^3$$He, $$^3$$He($$alpha$$,$$alpha_0$$) $$^3$$He and $$^3$$He($$alpha$$,p$$_0$$) $$^6$$Li reaction cross-sections. It is found that the present approach is necessary to obtain a reasonable description of all the measured data simultaneously. We also discuss the theoretical background for our recipe base on the physical aspects of the nuclear reactions.

Oral presentation

A Study on the safety of geological disposal of nitrate-containing waste, 2-1; The Exothermic measurement of the simulated waste and modeling heat flux

Mihara, Morihiro; Hara, Keiji*; Hasegawa, Kazutoshi*; Tochiyama, Osamu*; Adachi, Natsue*; Kirishima, Akira*

no journal, , 

no abstracts in English

Oral presentation

Numerical simulation of nitrate evolution in nitrate polluted groundwater using the model of nitrate evolution, 2

Abe, Toru*; Hirano, Fumio; Mihara, Morihiro; Honda, Akira

no journal, , 

no abstracts in English

Oral presentation

A Study on the safety of geological disposal of nitrate-containing waste, 2-2; Simulation study on the possibility of thermal reaction runaway after disposal

Nonaka, Kosuke*; Hirano, Fumio; Mihara, Morihiro; Hara, Keiji*; Tochiyama, Osamu*

no journal, , 

no abstracts in English

Oral presentation

International standardization of the education of cultures on nuclear safety and nuclear security

Hidaka, Akihide; Uesaka, Mitsuru*; Komatsuzaki, Tsuneo*; Takahashi, Makoto*; Okajima, Shigeaki; Uno, Masayoshi*

no journal, , 

no abstracts in English

Oral presentation

Development of nuclear transmutation methods for converting LLFP into stable or short-lived nuclides, 7; Neutron capture cross-section measurements of Cs and Se isotope nuclides

Nakamura, Shoji; Kimura, Atsushi; Hales, B. P.; Iwamoto, Osamu; Shibahara, Yuji*; Uehara, Akihiro*; Fujii, Toshiyuki*

no journal, , 

This presentation gives some progress about neutron capture cross section measurements of long-lived fission products, especially Cecium-135 under the ImPACT Project.

Oral presentation

Development of nuclear transmutation methods for converting LLFP into stable or short-lived nuclides, 16; Development of nuclear data library for the ImPACT project

Iwamoto, Osamu; Minato, Futoshi; Furutachi, Naoya; Iwamoto, Nobuyuki; Kunieda, Satoshi

no journal, , 

Under the ImPACT program of nuclear transmutation, we are developing a new nuclear data library that includes nuclear data of 4 main LLFPs ($$^{79}$$Se, $$^{93}$$Zr, $$^{107}$$Pd, $$^{135}$$Cs) and surrounding nuclei. To improve accuracy of nuclear data for unstable nuclei whose experimental data are scarce, microscopic nuclear structure theories was used to deduce nuclear level density and $$gamma$$-ray strength function. They were applied to evaluation of cross sections for neutron and proton induced reactions up to 200 MeV. Status of development of the library including evaluation methods and results is reported.

Oral presentation

Test of AMPX multigroup library for shielding in SCALE6.2.1

Konno, Chikara; Tada, Kenichi

no journal, , 

SCALE6.2.1 was released in 2016 and has been used worldwide. It includes new AMPX libraries (multigroup, continuous energy, ORIGEN, etc.) of ENDF/B-VII.0 and ENDF/B-VII.1. Now we investigate whether the self-shielding correction problem for resolved resonances, which was pointed out before, is revised in the AMPX multigroup library (scale.rev12.xn200g47v7.1, neutron 200 groups and $$gamma$$ 47 groups) for shielding. We also examine the self-shielding correction for unresolved resonances. Neutron and $$gamma$$ spectra inside an iron or arsenic sphere of 1 m in radius with a 20 MeV neutron source at the center were calculated with a one-dimensional Sn code ANISN. As a result, it was verified that the self-shielding correction of scale.rev12.xn200g47v7.1 for resolved resonances was not still correct. It was shown the self-shielding correction for unresolved resonances was similar to that with FRENDY, not NJOY.

Oral presentation

Study on criticality safety of directly disposed spent PWR fuel, 2; International benchmark on reflector effect of SiO$$_2$$

Suyama, Kenya; Akie, Hiroshi; Kataoka, Masaharu*; Yamamoto, Kento*

no journal, , 

no abstracts in English

Oral presentation

Advancement of airborne radiation measurement technology, 1; Contribution of position precision by GPS for manned helicopter monitoring

Mori, Airi; Sanada, Yukihisa; Seguchi, Eisaku; Kawabata, Tomoki; Munakata, Masahiro

no journal, , 

Count rates of radiation and the positional information (latitude, longitude, and height) are acquired simultaneously in airborne monitoring. The precision of positional information affects the air dose rates at 1 m height because air dose rates at 1 m height are calculated by correction of height. In this study, 3 GPS devices are used in addition to 1 GPS device which has been used in previous airborne monitoring. The most appropriate GPS device were determined by comparing precisions of positional information and influences on air dose rates at 1 m height.

Oral presentation

Development of nuclear transmutation methods for converting LLFP into stable or short-lived nuclides, 15; Level densities of LLFPs and nuclei around LLFPs calculated based on the microscopic structure calculation

Furutachi, Naoya; Minato, Futoshi; Iwamoto, Osamu

no journal, , 

To establish a reasonable nuclear transmutation technology for long-lived fission products (LLFPs), it is important to improve precision of the nuclear data needed for the simulation of the nuclear transmutation. The level density is essential for the nuclear reaction calculation using the statistical model, and it has significant influence on the precision of the nuclear data evaluation. Although a phenomenological model such as Fermi Gas model is used in a usual nuclear data evaluation, it is considered that using a microscopic theory that has predictive power superior to a phenomenological model brings better precision for the nuclear data. In this study, to improve precision of the nuclear data of LLFPs and nuclei around LLFPs, the level densities needed for the nuclear data evaluation of those nuclei were derived based on the microscopic nuclear data calculation. In this derivation, we improved the calculation method to describe prcisely the effect of the deformation change with nuclear excitation. To analyze precision of the nuclear reaction calculation, we compared the cross sections of various reaction channel systematically with the experimental data of stable nuclei.

Oral presentation

Behavior of radiolytic gas in zeolite bed under $$gamma$$-ray irradiation

Motooka, Takafumi; Yamagishi, Isao

no journal, , 

Mixtures of zeolite IE96 and artificial seawater (ASW) were poured in cylindrical tubes, and irradiated by Co-60 $$gamma$$-rays. In the case of a zeolite bed which was fully immersed in ASW, the zeolite bed level increased slightly (1.8%) and an ASW phase formed onto the bed. The ASW level increased with the irradiation dose. In the case of a partial immersion, which simulates a drained zeolite vessel, the zeolite bed level was un-changed (0.0%).

Oral presentation

Geochemical condition and solutes transport property around a closure tunnel

Iwatsuki, Teruki; Hayashida, Kazuki; Murakami, Hiroaki; Watanabe, Yusuke

no journal, , 

Geochemical condition and solutes transport property in and around a simulated closure tunnel were studied by observing the behavior of REEs at Mizunami Underground Research Laboratory. Results show that the REEs in the closure tunnel tend to be immobilized by absorbing to shotcrete and the colloidal flocculation.

Oral presentation

Direct beta-ray measurement of $$^{90}$$Sr adsorbed on fiber surface; Preparation of 18-crown 6-ether derivative-impregnated Sr adsorption fiber based on the radiation-induced graft polymerization

Horita, Takuma; Asai, Shiho; Konda, Miki; Hanzawa, Yukiko; Saito, Kyoichi*; Fujiwara, Kunio*; Kitatsuji, Yoshihiro

no journal, , 

There has been an increasing importance of the development of rapid separation techniques for $$^{90}$$Sr analysis, responding to needs in Fukushima Daiichi NPP. However, conventional $$^{90}$$Sr analytical methods require two different separation steps for Sr and Y, respectively, resulting in a long processing time of about one month. In this study, we prepared a Sr adsorptive fiber (Sr fiber) that has a high density Sr adsorption phase on its surface, allowing to highly efficient $$beta$$-ray counting by minimizing the self-attenuation effects. The adsorption capacity of the prepared Sr fiber was about 14 g/mol, which is equivalent to that of a commercially available Sr adsorptive resin (Sr Resin). The selectivity of the Sr fiber was nearly the same as that of the Sr resin. Considering that the Sr fiber has a specific surface area 1000 times smaller than that of the Sr Resin, the Sr ions can be concentrated to 1000 times on its surface, capable of achieving highly-efficient $$beta$$-ray counting. From these result, we confirmed that Sr fiber has adsorption capacity and selectivity necessary for highly efficient $$beta$$-ray counting of $$^{90}$$Sr.

279 (Records 1-20 displayed on this page)