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Mishima, Ria; Inaba, Yusuke*; Tachioka, Sotaro*; Harigai, Miki*; Watanabe, Shinta*; Onoe, Jun*; Nakase, Masahiko*; Matsumura, Tatsuro; Takeshita, Kenji*
Chemistry Letters, 49(1), p.83 - 86, 2020/01
Times Cited Count：4 Percentile：20.61(Chemistry, Multidisciplinary)Separation of platinum group metals (PGMs) from high-level liquid waste generated from the reprocessing of spent nuclear fuels is important to produce good quality vitrified glass for final disposal. A new sorbent, Aluminum hexacyanoferrate (AlHCF), was synthesized and the general sorption behavior of PGMs from concentrated nitric acid was examined. Nitric acid caused substantial elution of AlHCF but the sorption of Pd stabilized the structure. Consequently, Rh was sorbed in the presence of Pd, whereas single Rh sorption caused complete dissolution of AlHCF. Relation between sorbed mount of Pd vs eluted Al and Fe revealed that the elution ratio of Al and Fe was not the same as molar ratio of synthesized AlHCF, indicating the re-sorption of Fe resulted in formation of new structure. The sorption mechanism of PGMs by this new sorbent, AlHCF, not only the simple ion exchange, but also oxidation reduction reaction as well as kinetics play important rule. Understanding the general sorption and dissolution behavior will help improve the sorption performance of PGMs by AlHCF.
Onishi, Takashi; Sekioka, Ken*; Suto, Mitsuo*; Tanaka, Kosuke; Koyama, Shinichi; Inaba, Yusuke*; Takahashi, Hideharu*; Harigai, Miki*; Takeshita, Kenji*
Energy Procedia, 131, p.151 - 156, 2017/12
Times Cited Count：11 Percentile：98.82(Energy & Fuels)no abstracts in English
irradiation on the adsorption characteristics of xerogel microcapsulesOnishi, Takashi; Tanaka, Kosuke; Koyama, Shinichi; Ou, L. Y.*; Mimura, Hitoshi*
NEA/NSC/R(2017)3, p.463 - 469, 2017/11
no abstracts in English
Kokaji, Lisa; Suda, Kazunori; Tamai, Hiroshi; Tazaki, Makiko; Shimizu, Ryo
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-36-Kai Nenji Taikai Rombunshu (Internet), 7 Pages, 2015/12
After the Cold War, the United States and Russia have been decreasing the number of nuclear warheads under the Strategic Arms Reduction Treaty and other agreements, with step-by step removal from nuclear military programs under the process of nuclear disarmament. In 2000, the two states signed the Plutonium Management and Disposition Agreement (PMDA), which prescribes each of them to dispose of at least 34 metric tons of plutonium. Recently, since the cost of constructing the Mixed Oxide (MOX) Fabrication Facility has increased significantly, the United States has been assessing alternatives. In the revised PMDA, which defines weapon-grade plutonium as "an isotopic ratio of plutonium 240 to plutonium 239 of no more than 0.10", Article VII states, "Each Party shall have the right to conduct and the obligation to receive and facilitate monitoring and inspection activities", and Article VIII prescribes, "Each Party shall be responsible...for...disposition plutonium...taking into account...INFCIRC/225/Rev.4...". In accordance with the revised PMDA's obligation to dispose of an excess of 34 metric tons of plutonium, irradiation in fast reactors, irradiation of MOX fuel in LWRs, immobilization, downblending, and deep borehole options have been considered by the United States. In this research, it is examined how these options could be implemented from the nuclear nonproliferation and nuclear security perspectives.
Someya, Takaaki*; Asai, Shiho; Fujiwara, Kunio*; Sugo, Takanobu*; Umeno, Daisuke*; Saito, Kyoichi*
Nihon Kaisui Gakkai-Shi, 69(1), p.42 - 48, 2015/02
A large amount of seriously contaminated sea water with radioactive Cs has been reserved in semi-enclosed coastal sea area which is separated by silt fences and embankments. Insoluble cobalt ferrocyanide (Co-FC) microparticles-impregnated fiber was developed for removing Cs from the contaminated sea water. The resultant Co-FC-impregnated fiber was immersed in either nonradioactive or radioactive Cs solution. The adsorption isotherm well correlated with a Langmuir-type equation. In addition, mass-transfer capacity coefficients were determined by fitting the experimental data of the rate of Cs adsorption onto the Co-FC-impregnated fiber to theoretical adsorption curves based on the Cs concentration difference between the bulk and the interface in seawater as a driving force of the overall adsorption rate. Decontamination factors as functions of fiber weight and the contact time required for the removal of cesium ions from the contaminated seawater in a closed area were estimated.
Funasaka, Hideyuki; ;
JNC TN1200 2001-002, 209 Pages, 2001/01
JNC-TN1200-2001-002.pdf:7.84MB
no abstracts in English
Sugino, Kazuteru; Iwai, Takehiko*;
JNC TN9400 2000-098, 182 Pages, 2000/07
JNC-TN9400-2000-098.pdf:5.74MB
In order to support the Russian excess weapons plutonium disposition, the international collaboration has been started between Japan Nuclear Cycle Development Institute (JNC) and Russian Institute of Physics and Power Engineering (IPPE). In the frame of the collaboration, JNC has carried out analyses on the BFS-62 assemblies that are constructed in the fast reactor critical experimental facility BFS-2 of IPPE. This report summarizes an experimental analysis on the BFS-62-1 assembly, which is the first core of the BFS-62 series. The core contains the enriched U0
fuel surrounded by the U0 blanket. The standard analytical method for fast reactors has been applied, which was used for the JUPITER and other experimental analyses. Due to the lack of the analytical data the 2D RZ core calculation was mainly used. The 3D XYZ core calculation was applied only for the preliminary evaluation. Further in terms of the utilization of the BFS experimental analysis data for the standard data base for FBR core design, consistency evaluation with JUPITER experimental analysis data has been performed using the cross-section adjustment method. As the result of analyses, good agreement was obtained between calculations and experiments for the criticality and the reaction rate ratio. However, it was found that accurate evaluation of the reaction rate distribution was impossible without exact consideration of the arrangement of the two types of sodium (with and without hydrogen impurity), which can be accommodated by the 3D core analysis, thus it was essentia1. In addition, it was clarifie that there was a room for an improvement of the result on the reaction rate distribution in the blanket and shielding regions. The application of the 3D core calculation improved the result on the control rod worth because 3D core model can more exactly consider the shape of the control rod. Furthermore it was judged that the result of the analysis on the sodium void reactivity .....
; Sato, Wakaei*; Iwai, Takehiko*
JNC TN9400 2000-096, 113 Pages, 2000/06
This report describes the updated analyses results on the BFS-58-1-I1 core. The experiment was conducted at BFS-2 of Russian Institute of Physics & Power Engineering (IPPE). The central region is "non-Uranium fuel zone", where only Pu can induce fission reaction. The non-U zone is surrounded by MOx fuel zone, which is surrounded by U0 fuel zone. Sodium is used for simulating the coolant material. As it was found that the lattice pitch had been incorrectly understood in the past analyses, all items have been re-calculated using the corrected number densities. Furthermore, significantly softened neutron spectrum in the central region caused problems in applying the plate-stretch model that has been established for fast reactor cores through JUPITER experimental analyses. Both keeping the pellet density and using SRAC library for the elastic cross section for lighter nuclides allow us to obtain reasonable analysis accuracy on the spectral indices that were measured at the center of the core. Application of such a cell model was justified through comparison among various cell models using continuous energy Monte-Carlo code MVP. It is confirmed that both the MOX zone and the U0 zone can be correctly evaluated by the plate-stretch model. Based on the updated cell calculation, both the effective multiplication factor (k-eff)and the spectral indexes agree well with the measured values. The transport and mesh-size correction is made for the k-eff evaluation. Those results also agree well within reasonable difference between those obtained by IPPE and CEA, which were obtained by using sub-group method or continuous-energy Monte Carlo code. Evaluation by the nuclear data library adjustment confirmed that the analyses results of the BFS-58-1-I1 core have no significant inconsistency with JUPITER experimental analyses results. Those results are quite important for starting BFS-62 cores, which will be analyzed in the framework of supporting program for Russian ...
Nuclear Non-Proliferation Study Group*; *; Iwata, Shuichiro*; *; *; *;
JNC TN1400 2000-008, 81 Pages, 2000/04
JNC-TN1400-2000-008.pdf:3.44MB
no abstracts in English
Mochiji, Toshiro;
JNC TN1450 2000-001, 122 Pages, 2000/03
JNC-TN1450-2000-001.pdf:6.39MB
no abstracts in English
Mochiji, Toshiro;
JNC TN1200 2000-001, 13 Pages, 2000/03
JNC-TN1200-2000-001.pdf:2.94MB
no abstracts in English
Otagaki, Takao*; *
JNC TJ8420 2000-016, 427 Pages, 2000/03
JNC-TJ8420-2000-016.pdf:18.18MB
no abstracts in English
+L intensities of 3d-transition metals in phthalocyanines and the amine complexesKoshino, M.*; Kurata, Hiroki; Isoda, Shoji*; Kobayashi, Takashi*
Micron, 31(4), p.373 - 380, 2000/03
Times Cited Count：12 Percentile：18.81(Microscopy)no abstracts in English
*
JNC TN1440 2000-001, 47 Pages, 2000/01
JNC-TN1440-2000-001.pdf:2.57MB
no abstracts in English
Hunter
JNC TN9400 99-049, 74 Pages, 1999/04
This document describes a series of calculations that were carried out to model various measurements from the BFS-58-1-I1 experiment. BFS-58-1-I1 was a mock-up of a uranium-free, Pu burning core at BFS-2, a Russian critical assembly operated by IPPE. The experiment measured values of keff, Na void reactivity worth, material sample reactivity worths and reaction rate ratios. The experiments were modelled using a number of different methods. Basic nuclear data was taken from JENDL-3.2, in either 70 or 18 groups. Cross-section data for the various material regions of the assembly were calculated by either SLAROM or CASUP; the heterogeneous structure of the core regions was modelled in these calculations, with 3 different options considered for representing the (essentially 2d) geometry of the assembly components in a 1D cell model. Whole reactor calculations of flux and keff were done using both a diffusion model (CITATION) and a transport model (TWOTRAN2), both using an RZ geometry. Reactivity worths were calculated both directly from differences in keff values and by using the exact perturbation calculations of PERKY and SN-PERT (for CITATION and TWOTRAN2, respectively). Initial calculations included a number of inaccuracies in the assembly representation, a result of communication difficulties between JNC and IPPE; these errors were removed for the final calculations that are presented. Calculations for the experiments have also been carried out in Russia (IPPE) and France (CEA) as part of an international comparison exercise, some of those results are also presented here. The calculated value of keff was 1.1%
k/k higher than the measured value, Na void worth C/E values were 
1.06; these results were considered to be reasonable. (Discrepancies in certain Na void values were probably due to experimental causes, though the efect should be investigated in any future experiments.) several sample worth values were small compared with calculational uncertaint
Robin E*
PNC TN1410 98-008, 39 Pages, 1998/05
The 3rd international forum on nuclear non-proliferation was held on 23-25 February 1998 at the Nadao hall of the Shin-kasumigaseki building, in Tokyo, Japan. The forum was organized by the nuclear non-proliferation study group. It was the goal of the nuclear non-proliferation study group to create a forum program that would be both interesting and informative. After some examination, the study group felt that the topics of most interest were the pursuit of the compatibility of the peaceful use of nucleare nergy and the maintenance of the non-proliferation regime. Another area receiving much attention as of late is the disposition of excess weapons plutonium. To address these areas, the forum was divided into three sessions and a special full day session which was devoted completely to the plutonium disposition issue. The first session tackled the peaceful use of plutonium. The second session discussed the issues and the recent situation of the non-proliferation regime. The third ...
