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Hidaka, Akihide
Fission Product Behavior under Severe Accident, p.85 - 88, 2021/05
no abstracts in English
Iino, Mari*; Onuma, Susumu*; Hirose, Yukio*; Osawa, Hideaki; Otomo, Shoji*
Nihon Risuku Kenkyu Gakkai-Shi, 29(2), p.95 - 102, 2019/10
The purpose of this research is to investigate the effects of compensation framing on acceptance of a high level radioactive waste (HLW) geological repository. The results demonstrated that there were no main effects of condition, which suggested that the framing of compensation had no significant impact on acceptance of a HLW geological repository.
Amano, Hikaru; Takahashi, Tomoyuki*; Uchida, Shigeo*; Matsuoka, Shungo*; Ikeda, Hiroshi*; Hayashi, Hiroko*; Kurosawa, Naohiro*
JAERI-Conf 2003-010, p.112 - 121, 2003/09
The functionality of MOGRA is being verified by applying it in the analyses of the migration rates of radioactive substances from the atmosphere to soils and plants and flow rates into the rivers. This has been achieved by also taking their mode classifications into consideration. In this report, a hypothetical combination of land usage was supposed to check the function of MOGRA. The land usage was consisted from cultivated lands, forests, uncultivated lands, urban area, river, and lake. Each land usage has its own inside model which is basic module. Also supposed was homogeneous contamination of the surface land from atmospheric deposition of Cs-137 (1.0 Bq/m
). The system can analyze the dynamic changes of Cs-137 concentrations in each compartment, fluxes from one compartment to another compartment.
CO
and their fluxes from surface environment with a development of a simultaneous sampling system for the speciation of atmospheric H-3 and C-14Amano, Hikaru; Koarashi, Jun*; Koma, T.*; Atarashi-Andoh, Mariko; Iida, Takao*
JAERI-Conf 2003-010, p.221 - 225, 2003/09
Concerning atmospherically released tritium (T) and C-14 we have developed a new method, which can analyze their fluxes and the deposition velocities. Firstly, a simultaneous sampling system for the speciation of atmospheric tritium and C-14 has been developed. This system determines varieties of chemical forms of tritium and C-14, namely tritiated water (HTO), elemental tritium gas (HT) and tritiated methane (CH
T) for tritium, CO and 14C H4 for C-14, respectively. Secondly, a new method was developed to determine HT and CO deposition velocities. This method can determine their fluxes and the deposition velocities without any tritium and C-14 sources.
Narumi, Issei
Trends in Microbiology, 11(9), p.422 - 425, 2003/09
Times Cited Count：51 Percentile：89.9(Biochemistry & Molecular Biology)no abstracts in English
Amano, Hikaru; Onuma, Yoshikazu*
Journal of Radioanalytical and Nuclear Chemistry, 255(1), p.217 - 222, 2003/01
Times Cited Count：8 Percentile：49.89(Chemistry, Analytical)no abstracts in English
Sakamoto, Yoshiaki; Ishii, Tomoaki*; Inagawa, Satoshi*; Gunji, Yasuyoshi*; Takebe, Shinichi; Ogawa, Hiromichi; Sasaki, Tomozo*
Journal of Nuclear Science and Technology, 39(Suppl.3), p.481 - 484, 2002/11
Sorption behavior of 227Ac and 233Pa onto several kinds of soils has been studied with a sequential extraction technique, for safety assessment of shallow land disposal of uranium bearing waste. After a batch sorption experiment, the sorbed form of 227Ac and 233Pa onto the soils was fractionated into ion exchange form (extraction by KCl+CaCl2), association with Fe+Mn oxides (extraction by NH2OH-HCl and oxalic acid), association with organic materials (extraction by H2O2) and fixation into soil (residual). From the results of the sequential extraction, major part of 227Ac sorbed onto the soils was found in the fraction of the ion exchange form and the fixation into the soils. On the other hand, major part of 233Pa was found in the fraction of the association with Fe+Mn oxides and the fixation into the soils. These results suggest that the sorption behavior of 227Ac and 233Pa is related to the irreversible sorption reaction onto the soils.
Zhu, X. D.; Naramoto, Hiroshi; Xu, Y.; Narumi, Kazumasa; Miyashita, Kiyoshi*
Journal of Chemical Physics, 116(23), p.10458 - 10461, 2002/06
Times Cited Count：5 Percentile：14.82(Chemistry, Physical)no abstracts in English
Kakiuchi, Hideki; Amano, Hikaru; Ichimasa, Michiko*
Journal of Radioanalytical and Nuclear Chemistry, 252(2), p.437 - 439, 2002/05
Times Cited Count：6 Percentile：39.54(Chemistry, Analytical)no abstracts in English
Matsunaga, Takeshi; Nagao, Seiya*; Takeda, Seiji; Ueno, Takashi; Amano, Hikaru
Dai-43-Kai Kankyo Hoshano Chosa Kenkyu Seika Rombun Shorokushu (Heisei-12-Nendo), p.49 - 50, 2002/03
no abstracts in English
Kobayashi, Kaoru*; Kaminaga, Masanori; Haga, Katsuhiro; Kinoshita, Hidetaka; Aso, Tomokazu; Teshigawara, Makoto; Hino, Ryutaro
JAERI-Tech 2002-005, 118 Pages, 2002/02
JAERI-Tech-2002-005.pdf:9.71MB
In order to examine the radiation safety of a spallation mercury target system, it is necessary to clarify the chemical forms of spallation products generated by spallation reaction with proton beam. As for the chemical forms of spallation products in mercury that involves large amounts of spallation products, these forms were estimated by using the binary phase diagrams and the thermochemical equilibrium calculation based on the amounts of spallation product. Calculation results showed that the mercury would dissolve Al, As, B, Be, Bi, C, Co, Cr, Fe, Ga, Ge, Ir, Mo, Nb, Os, Re, Ru, Sb, Si, Ta, Tc, V and W in the element state, and Ag, Au, Ba, Br, Ca, Cd, Ce, Cl, Cs, Cu, Dy, Er, Eu, F, Gd, Hf, Ho, I, In, K, La, Li, Lu, Mg, Mn, Na, Nd, Ni, O, Pb, Pd, Pr, Pt, Rb, Rh, S, Sc, Se, Sm, Sn, Sr, Tb, Te, Ti, Tl, Tm, Y, Yb, Zn and Zr in the form of inorganic mercury compounds.
Amano, Hikaru
Hoken Butsuri, 36(4), p.314 - 321, 2001/12
no abstracts in English
Amano, Hikaru; *; Uchida, Shigeo*; Tsuzuki, Katsunori; Matsuoka, Shungo*; Ikeda, Hiroshi*; Matsubara, Takeshi*; Kurosawa, Naohiro*
KURRI-KR-80, p.48 - 49, 2001/12
no abstracts in English
Hama, Katsuhiro; Taniguchi, Naoki; Honda, Akira
JNC TN7430 2000-002, 25 Pages, 2001/01
JNC-TN7430-2000-002.pdf:3.32MB
The burial tests of mild steel and pure titanium were performed in a gallery at Tono mine to assess the corrosion resistance of these materials under goundwater environment. Specimens were placed in the container and immersed into groundwater. After the immersion period, the apperance of the surface of these specimens were observed. The corrosion product of mild steel specimen was analysed by various methods. The average corrosion rate of mild steel for 10 years was assessed by the measurement of the weight loss of carbon steel specimen. The results of the test were summerised as follows : (1)The average corrosion rate of mild steel for 10 years was assessed to be 4.36 
10
mm/y by the weight loss of the specimen. (2)The corrosion product consists of outer porous substance and inner tight corrosion product film. The former contains ferric oxide such as goethite and the latter contains ferrous oxide such as magnetite. (3)The evidence of the initiation of localised corrosion was not observed on the titanium specimens.
; Inagaki, Tatsutoshi*
JNC TY1400 2000-004, 464 Pages, 2000/08
JNC-TY1400-2000-004.pdf:19.55MB
None
; Inagaki, Tatsutoshi*
JNC TY1400 2000-003, 92 Pages, 2000/08
Japan Nuclear Cycle Development Institute (JNC) and Japan Atomic Power company (JAPCO, that is the representative of the electric utilities in Japan) have established a new organization to develop a commercialized fast breeder reactor (FBR) cycle system since July 1, 1999 and feasibility studies (F/S) have been undertaken in order to determine the promising concepts and to define the necessary R&D tasks. In the first two-year phase, a number of candidate concepts will be selected from various options, featuring innovative technologies. In the F/S, the options are evaluated and conceptual designs are examined considering the attainable perspectives for following: (1) ensuring safety, (2) economic competitiveness to future LWRs, (3) efficient utilization of resources, (4) reduction of environmental burden and (5) enhancement of nuclear non-proliferation. The F/S should also guide the necessary R&D to commercialize FBR cycle system.
Koshizuka, Seiichi*; *; Okano, Yasushi; *; Yamaguchi, Akira
JNC TY9400 2000-012, 91 Pages, 2000/03
JNC-TY9400-2000-012.pdf:2.82MB
no abstracts in English
Yamanaka, Shinsuke*; Abe, Kazuyuki
JNC TY9400 2000-004, 78 Pages, 2000/03
JNC-TY9400-2000-004.pdf:2.39MB
no abstracts in English
Oki, Shigeo; Iwai, Takehiko*; Jin, Tomoyuki*
JNC TN9400 2000-080, 532 Pages, 2000/03
JNC-TN9400-2000-080.pdf:14.98MB
Transmutation Property of minor actinide nuclides (MA) was analyzed for fast reactor cores having different coolant and fuel types in order to obtain basic data for evaluating an ability of the efficient use of resource and reducing the effect on the environment. The investigated fast reactor cores were (a) sodium cooled and oxide fueled core, (b) lead cooled and nitride fueled core (BREST-300), (c) carbon dioxide gas cooled and oxide fueled core (ETGBR), (d)lead cooled and oxide fueled core, (e) sodium cooled and nitride fueled core (both He-bond and sodium-bond), and (f) sodium cooled and metallic fueled core. Followings were observed for the relation between MA transmutation property and the different types of coolant and fuel of fast reactor core. (1) For the MA transmutation rate, the relation "Oxide 
Metal Nitride" was found out for difference of fuel type. A main reason of the increment of MA transmutation rate is that the neutron flux level rises on nitride and metallic fueled cores in comparison with oxide core. (2) The relation "Lead Sodium and Carbon dioxide" can be seen for the MA transmutation rate in the difference of coolant, but it is not clear whether the cause is driven from the difference of coolant itself on the difference of core design. (3) The changes of MA transmutation property mentioned above are comparatively small.
*; Sato, Seiji*; *; Naruki, Kaoru
JNC TJ1400 2000-010, 71 Pages, 2000/03
JNC-TJ1400-2000-010.pdf:2.11MB
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