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JAEA Reports

JENDL decay data file 2015

Katakura, Junichi*; Minato, Futoshi

JAEA-Data/Code 2015-030, 97 Pages, 2016/03

JAEA-Data-Code-2015-030.pdf:1.01MB

JENDL Decay Data File 2015 (JENDL/DDF-2015) has been produced. The decay data of nuclides with mass numbers from 1 to 260 are included. The nuclides with unknown - and/or beta-emission are also included in order to keep decay chains. The data of 1,284 fission product nuclides with mass from 66 to 172 remain unchanged from JENDL/FPD-2011 except several corrections which had been claimed by users, and those of the newly added 1,953 nuclides are taken from ENSDF. Finally, the decay data of 3,237 nuclides including 244 stable nuclides were compiled as JENDL/DDF-2015 file.

Journal Articles

Revision of the JENDL FP fission yield data

Katakura, Junichi*; Minato, Futoshi; Ohgama, Kazuya

EPJ Web of Conferences, 111, p.08004_1 - 08004_5, 2016/03

https://doi.org/10.1051/epjconf/201611108004

Times Cited Count：17 Percentile：99.54(Nuclear Science & Technology)

The JENDL FP Fission Yield Data Library (JENDL/FPY-2011) was released in 2011. Although the data of the yield file are successfully applied to decay heat summation calculations, there have been reported some inadequacies when applied to delayed neutron related subjects. And also from sensitivity analyses of summation calculation, some fission yield data in the JENDL file have been claimed to have some problems. In order to remedy those problems some yield data of the JENDL file have been re-examined and revised. The following is one example. The yield data of $^{86}$ Ge for thermal neutron fission of $^{235}$ U is given to be 6.277 $times10^{-3}$ in JENDL/FPY-2011 which has been claimed to be too large. The re-examination and re-calculation of the fission yield data now give the new value of 3.437 $times10^{-6}$ which seems to be more reasonable. There are some other nuclides indicated by the sensitivity analyses. The process of the re-examination of those nuclides and the revised yield data will be presented in the workshop WONDER 2015.

Journal Articles

Compilation for chart of the nuclides 2014; A Comprehensive decay data

Koura, Hiroyuki; Katakura, Junichi*; Tachibana, Takahiro*; Minato, Futoshi

JAEA-Conf 2015-003, p.147 - 152, 2016/03

https://doi.org/10.11484/jaea-conf-2015-003

A chart of the nuclides 2014 version is now preparing to be published from JAEA. This will be the latest successive version of the chart since 1977, and continues every (approximately) four years until 2010. These charts include decay data of isotopes as half-lives, decay modes, and some isomeric states. In addition, the periodic table of elements, fundamental physical constants, thermal neutron capture and fission cross sections are tabulated. The latest version is now compiled with recent experimental data until the end of June in 2014. In the compilation process, we improved in the following parts: (1) Neutron or proton-unbound nuclei in the lighter region. (2) Drawing the neutron and proton-drip lines, and a boundary line of -delayed neutron emission. (3) 1- or 2-proton-emission theoretical half-lives are added for unmeasured nuclei in addition to original three partial half-lives of -decay, -decay and spontaneous fission. We compiled totally 3150 nuclides, which were experimental identified including 2914 life-measured nuclei. We will show overview of the chart with some statistics and examples.

Journal Articles

Interfacial analysis of surface-coated LiMn $_{2}$ O $_{4}$ epitaxial thin film electrode for lithium batteries

Suzuki, Kota*; Hirayama, Masaaki*; Kim, K.-S.*; Taminato, So*; Tamura, Kazuhisa; Son, J.-Y.*; Mizuki, Junichiro; Kanno, Ryoji*

Journal of the Electrochemical Society, 162(13), p.A7083 - A7090, 2015/08

https://doi.org/10.1149/2.0111513jes

Times Cited Count：11 Percentile：36.55(Electrochemistry)

The effects of surface coatings on LiMn $_{2}$ O $_{4}$ were investigated using LiMn $_{2}$ O $_{4}$ epitaxial thin films with a thickness of 30 nm. Bare and surface-coated LiMn $_{2}$ O $_{4}$ epitaxial thin films were synthesized on SrTiO $_{3}$ (111) substrates using a pulsed laser deposition method. The surface coating, which was formed using the solid electrolyte Li $_{3}$ PO $_{4}$ and had a thickness of 3 nm, improved the reversibility of the electrochemical reactions undergone by the LiMn $_{2}$ O $_{4}$ epitaxial thin films. The changes induced in the surface structure were maintained during battery operation; in contrast, the bare LiMn $_{2}$ O $_{4}$ thin film exhibited structural degradation and Mn dissolution. The structural changes induced in the coated electrode and the increase in its surface stability were intrinsic effects of the Li $_{3}$ PO $_{4}$ coating and improved the electrochemical performance of the LiMn $_{2}$ O $_{4}$ thin-film electrode.

Journal Articles

Mechanistic studies on lithium intercalation in a lithium-rich layered material using Li $_{2}$ RuO $_{3}$ epitaxial film electrodes and surface X-ray analysis

Taminato, So*; Hirayama, Masaaki*; Suzuki, Kota*; Kim, K.-S.*; Zheng, Y.*; Tamura, Kazuhisa; Mizuki, Junichiro; Kanno, Ryoji*

Journal of Materials Chemistry A, 2(34), p.17875 - 17882, 2014/11

https://doi.org/10.1039/C4TA02795G

Times Cited Count：21 Percentile：55.49(Chemistry, Physical)

The surface structure of a lithium-rich layered material and its relation to intercalation properties were investigated by synchrotron X-ray surface structural analyses using Li $_{2}$ RuO $_{3}$ epitaxial-film model electrodes with different lattice planes of (010) and (001). Electrochemical charge-discharge measurements confirmed reversible lithium intercalation activity through both planes, corresponding to three-dimensional lithium diffusion within the Li $_{2}$ RuO $_{3}$ . The (001) plane exhibited higher discharge capacities compared to the (010) plane under high rate operation (over 5 C). Direct observations of surface structural changes by surface X-ray diffraction (XRD) and surface X-ray absorption near edge structure (XANES) established that an irreversible phase change occurs at the (010) surface during the first (de)intercalation process, whereas reversible structural changes take place at the (001) surface.

Journal Articles

Characterization of nano-sized epitaxial Li $_{4}$ Ti $_{5}$ O $_{12}$ (110) film electrode for lithium batteries

Kim, K.-S.*; Tojigamori, Takeshi*; Suzuki, Kota*; Taminato, So*; Tamura, Kazuhisa; Mizuki, Junichiro; Hirayama, Masaaki*; Kanno, Ryoji*

Denki Kagaku Oyobi Kogyo Butsuri Kagaku, 80(10), p.800 - 803, 2012/10

https://doi.org/10.5796/electrochemistry.80.800

Times Cited Count：12 Percentile：29.96(Electrochemistry)

Electrochemical properties and structure changes of nano-sized Li $_{4}$ Ti $_{5}$ O $_{12}$ during lithium (de)intercalation wereinvestigated using a two-dimensional thin film electrode. Li $_{4}$ Ti $_{5}$ O $_{12}$ thin films were deposited on a Nb:SrTiO $_{3}$ (110)substrate by a pulsed laser deposition technique. In situ X-ray diffraction measurements clarified the drastic structural changes of the Li $_{4}$ Ti $_{5}$ O $_{12}$ film upon soaking in the electrolyte and during the first intercalation and deintercalation processes. The surfaceregion of Li $_{4}$ Ti $_{5}$ O $_{12}$ had a different structure from the bulk during electrochemical cycling and could cause the nanosizedLi $_{4}$ Ti $_{5}$ O $_{12}$ electrodes to have high capacities and poor stabilities.

Journal Articles

Actinide-handling experience for training and education of future expert under J-ACTINET

Osaka, Masahiko; Konashi, Kenji*; Hayashi, Hirokazu; Li, D.*; Homma, Yoshiya*; Yamamura, Tomoo*; Sato, Isamu; Miwa, Shuhei; Sekimoto, Shun*; Kubota, Takumi*; et al.

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 5 Pages, 2011/12

Summer schools for future experts have successfully been completed under Japan Actinide Network (J-ACTINET) for the purpose of development of human resources who are expected to be engaged in every areas of actinide-research/engineering. The first summer school was held in Ibaraki-area in August 2009, followed by the second one in Kansai-area in August 2010. Two summer schools have focused on actual experiences of actinides in actinide-research fields for university students and young researchers/engineers as an introductory course of actinide-researches. Several quasi actinide-handling experiences at the actinide-research fields have attracted attentions of participants at the first school in Ibaraki-area. The actual experiments using actinides-containing solutions have been carried out at the second school in Kansai-area. Future summer schools will be held every year for the sustainable human resource development in various actinide-research fields.

Journal Articles

Flexible fuel cycle R&D for the smooth FBR deployment

Fukasawa, Tetsuo*; Yamashita, Junichi*; Hoshino, Kuniyoshi*; Sasahira, Akira*; Inoue, Tadashi*; Minato, Kazuo; Sato, Seichi*

Proceedings of 16th Pacific Basin Nuclear Conference (PBNC-16) (CD-ROM), 6 Pages, 2008/10

Transition period from light water reactors (LWR) to fast breeder reactors (FBR) is quite important to achieve the future FBR cycle system. The transition scenarios were carefully studied and the Flexible Fuel Cycle Initiative (FFCI) was proposed in this study. FFCI carries out about 90% uranium (U) removal from LWR spent fuels (SF) at first and then recovers plutonium/uranium (Pu/U) from the remaining SF named "recycle material"(RM) (about 40% U, 15% Pu and 45% other nuclides) for FBR fresh fuel fabrication according to the FBR deployment status. The FFCI has some merits compared with ordinary system that carries out full reprocessing of LWR SF, that is volume reduction of LWR SF by its conversion to RM (proliferation resistant material), and storage and supply of high Pu density RM according to FBR deployment rate changes.

Journal Articles

Uranium recovery in LWR reprocessing and plutonium/residual uranium conditioning in FBR reprocessing for the transition from LWR to FBR

Fukasawa, Tetsuo*; Yamashita, Junichi*; Hoshino, Kuniyoshi*; Sasahira, Akira*; Inoue, Tadashi*; Minato, Kazuo; Sato, Seichi*

Proceedings of 3rd International ATALANTE Conference (ATALANTE 2008) (CD-ROM), 7 Pages, 2008/05

In order to flexibly manage the transition period from LWR to FBR, the authors investigated the transition scenario and proposed the Flexible Fuel Cycle Initiative (FFCI). In FFCI, LWR spent fuel reprocessing only carries out the removal of about 90% uranium that will be purified and utilized in LWR after re-enrichment. The residual material (40% U, 15% Pu and 45% other nuclides) is transferred to temporary storage and/or FBR spent fuel reprocessing to recover Pu/U followed by FBR fresh fuel fabrication depending on the FBR introduction status. The FFCI has some merits compared with ordinary system that consists of full reprocessing facilities for both LWR and FBR spent fuels, that is smaller LWR reprocessing facility, spent LWR fuel reduction, storage and supply of high proliferation resistant and high Pu density material that can flexibly respond to FBR introduction rate changes. The Pu balance was calculated under several cases, which revealed that the FFCI could supply enough Pu to FBR in any cases.

JAEA Reports

Status and future plan of research and development on partitioning and transmutation technology for long-lived nuclides in JAERI

Oigawa, Hiroyuki; Nishihara, Kenji; Minato, Kazuo; Kimura, Takaumi; Arai, Yasuo; Morita, Yasuji; Nakayama, Shinichi; Katakura, Junichi

JAERI-Review 2005-043, 193 Pages, 2005/09

JAERI-Review-2005-043.pdf:16.13MB

JAERI has been conducting research and development on partitioning and transmutation (P&T) technology for long-lived nuclides to develop the double-strata fuel cycle concept, in accordance with the Atomic Energy Commission's "Research and Development of Technologies for Partitioning and Transmutation of Long-lived Nuclides - Status and Evaluation Report" issued in 2000. The double-strata fuel cycle concept consists of four major processes: partitioning, fuel fabrication, transmutation, and fuel processing. The five-year achievement and future perspectives for the technology on these processes are presented in this report. It also provides an analytical study on impacts of introducing P&T technology on waste management, and on deployment of P&T for the future nuclear energy system.

Journal Articles

Arsenate sorption on schwertmannite

Fukushi, Keisuke*; Sato, Tsutomu*; Yanase, Nobuyuki; Minato, Junichi*; Yamada, Hirohisa*

American Mineralogist, 89(11-12), p.1728 - 1734, 2004/11

http://ammin.geoscienceworld.org/content/89/11-12/1728.abstract

The sorption mechanism of As(V) on schwertmannite was investigated by both a batch sorption experiment and crystallographic considerations. The batch experiment was carried out as a function of As(V) concentration in acidic solution at 25 $^{circ}$ C. Crystallographic considerations indicate surface sites of schwertmannite comprise varied surface oxygen (hydroxyl) and SO $_{4}$ groups. Sorption experiments showed reactive surface sites for As(V) sorption are surface SO $_{4}$ groups. As(V) sorption mechanism involves ligand exchange with solid phase SO $_{4}$ . Results also suggest monodentate As(V) coordination with surface adsorbed SO $_{4}$ sites and bidentate As(V) coordination in structural originated SO $_{4}$ sites. Estimated equilibrium constant for ligand exchange reaction describes the observed As(V) sorption behavior. The surface structure approach in this study reveals reactive surface sites in As(V) sorption on schwertmannite comprise surface SO $_{4}$ group instead of surface hydroxyl groups identified by former views.