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Journal Articles

Phase-transition kinetics of magnetic skyrmions investigated by stroboscopic small-angle neutron scattering

Nakajima, Taro*; Inamura, Yasuhiro; Ito, Takayoshi*; Oishi, Kazuki*; Oike, Hiroshi*; Kagawa, Fumitaka*; Kikkawa, Akiko*; Taguchi, Yasujiro*; Kakurai, Kazuhisa*; Tokura, Yoshinori*; et al.

Physical Review B, 98(1), p.014424_1 - 014424_5, 2018/07

 Times Cited Count:4 Percentile:32.53(Materials Science, Multidisciplinary)

We investigated the phase-transition kinetics of magnetic skyrmion lattice (SkL) in MnSi by means of stroboscopic small-angle neutron scattering (SANS). Temporal evolutions of SANS patterns were measured with time resolution of 13 ms while sweeping temperature as fast as 50 Ks$$^{-1}$$. It turned out that the paramagnetic-to-SkL transition immediately occurs upon traversing the equilibrium phase boundary on the rapid cooling, whereas the SkL-to-conical transition can be kinetically avoided to realize the low-temperature metastable SkL with a long-range magnetic order. The formation of the metastable SkL was found to be strongly dependent not only on cooling rate, but also on magnetic eld and trajectory in the H-T phase diagram.

Journal Articles

Production of criticality safety standard data with Monte-Carlo code MVP / nuclear data library JENDL-3.2 validated using ICSBE data

Tonoike, Kotaro; Suyama, Kenya; Okuno, Hiroshi; Miyoshi, Yoshinori; Uchiyama, Gunzo

Proceedings of 9th International Conference on Nuclear Criticality (ICNC 2011) (CD-ROM), 8 Pages, 2012/02

The 1st version of criticality safety handbook of Japan was published in 1988. A criticality safety analysis code system JACS was validated, and minimum critical mass and safety limit mass of various fissile materials were calculated. During more than two decades since then, new critical experimental data were taken in the Static Critical Experiment Facility (STACY), and more precise benchmark data of wider range of fissile materials were accumulated by the International Criticality Safety Benchmark Evaluation Project (ICSBEP). Computational capability has greatly grown, and new codes and nuclear data have been developed. The 2nd version of the handbook utilizes the results of validation of the criticality analysis method with a continuous energy Monte-Carlo code MVP and a nuclear data library JENDL-3.2 using the benchmark data chosen from the ICSBEP handbook. Results of the benchmark calculation were statistically studied, from which the safety limit value of multiplication factor was derived as 0.98. Based on the conclusion, minimum critical mass and safety limit mass were calculated. Future plan of research activities on the criticality safety in JAEA will be also overviewed.

JAEA Reports

Second version of data collection part of nuclear criticality safety handbook (Contract research)

Okuno, Hiroshi; Suyama, Kenya; Tonoike, Kotaro; Yamane, Yuichi; Yamamoto, Toshihiro; Miyoshi, Yoshinori; Uchiyama, Gunzo

JAEA-Data/Code 2009-010, 175 Pages, 2009/08

JAEA-Data-Code-2009-010.pdf:13.1MB
JAEA-Data-Code-2009-010(errata).pdf:0.11MB

The report revised the Data Collection part of Nuclear Criticality Safety Handbook, which was published in 1988. This second version provided criticality data on homogeneous U-H$$_{2}$$O and UF$$_{6}$$-HF, which were not cited in the previous version, and increased those data on the medium-enriched uranium fuels. Calculations were performed mainly with the Continuous-Energy Monte Carlo Criticality Calculation Code, MVP, and the Japanese Evaluated Nuclear Data Library, JENDL-3 Revision 2, JENDL-3.2, both of which were developed at the late Japan Atomic Energy Research Institute (JAERI). Data on atomic number densities of actinide metal and oxide were additionally supplied, and nuclide compositions of irradiated fuels were improved from the first version. One million histories of neutrons were followed in benchmark calculations of critical experiments and in calculations of single-unit criticality data, i.e., critical mass, volume, dimensions, etc., to attain almost ten times higher precision than the first version.

Journal Articles

Nuclear criticality safety aspects of "specified"-uranium fuel cycle facilities

Okuno, Hiroshi; Suyama, Kenya; Takahashi, Satoshi*; Watanabe, Shoichi*; Tonoike, Kotaro; Miyoshi, Yoshinori

Transactions of the American Nuclear Society, 95(1), p.283 - 284, 2006/11

no abstracts in English

Journal Articles

Revised data for 2nd version of Nuclear Criticality Safety Handbook/Data Collection

Okuno, Hiroshi; Ryufuku, Susumu*; Suyama, Kenya; Nomura, Yasushi; Tonoike, Kotaro; Miyoshi, Yoshinori

JAERI-Conf 2003-019, p.116 - 121, 2003/10

This paper outlines the data prepared for the 2nd version of Data Collection of the Nuclear Criticality Safety Handbook. These data are discussed in the order of its preliminary table of contents. The nuclear characteristic parameters (k$$_{rm inf}$$, M$$^{2}$$, D) were derived, and subcriticality judgment graphs were drawn for eleven kinds of fuels which were often encountered in criticality safety evaluation of fuel cycle facilities. For calculation of criticality data, benchmark calculations using the combination of the continuous energy Monte Carlo criticality code MVP and the Japanese Evaluated Nuclear Data Library JENDL-3.2 were made. The calculation errors were evaluated for this combination. The implementation of the experimental results obtained by using NUCEF facilities into the 2nd version of the Data Collection is under discussion. Therefore, related data were just mentioned. A database is being prepared to retrieve revised data easily.

Journal Articles

Burnup importance function and its application to OECD/NEA/BUC phase II-A and II-C models

Okuno, Hiroshi; Tonoike, Kotaro; Sakai, Tomohiro*

Proceedings of International Conference on the New Frontiers of Nuclear Technology; Reactor Physics, Safety and High-Performance Computing (PHYSOR 2002) (CD-ROM), 8 Pages, 2002/10

As the burnup proceeds, reactivity of fuel assemblies for light water reactors decreases by depletion of fissile nuclides, especially in the axially central region. In order to describe the importance of the end regions to the reactivity change, a burnup importance function was introduced as a weighting function to a local burnup variation contributed to a reactivity decrease. The function was applied to the OECD/NEA/BUC Phase II-A model and a simplified Phase II-C model. The application to Phase II-A model clearly showed that burnup importance of the end regions increases as burnup and/or cooling time increases. Comparison of the burnup importance function for different initial enrichments was examined. The application result to the simplified Phase II-C model showed that the burnup importance function was helpful to find the most reactive fuel burnup distribution under the conditions that the average fuel burnup was kept constant and the variations in the fuel burnup were within the maximum and minimum measured values.

JAEA Reports

Annual report of STACY operation in FY. 2000; Experiments on neutron-interacting systems with two slab-shaped core tanks and 10% enriched uranyl nitrate solution, 2 (Contract research)

Onodera, Seiji; Hirose, Hideyuki; Izawa, Kazuhiko; Tanino, Shuichi; Kaminaga, Jota*; Sakuraba, Koichi; Miyauchi, Masakatsu; Tonoike, Kotaro; Miyoshi, Yoshinori; Yanagisawa, Hiroshi; et al.

JAERI-Tech 2001-057, 54 Pages, 2001/09

JAERI-Tech-2001-057.pdf:4.28MB

no abstracts in English

JAEA Reports

Annual report of STACY operation in FY.1999; Experiments on two unit neutron-interacting system with slab-shaped core tanks and 10% enriched uranyl nitrate solutions, 1 (Contract research)

Onodera, Seiji; Sono, Hiroki; Hirose, Hideyuki; Tanino, Shuichi; Kaminaga, Jota*; Myomae, Tomoki*; Murakami, Kiyonobu; Sakuraba, Koichi; Miyauchi, Masakatsu; Tonoike, Kotaro; et al.

JAERI-Tech 2000-059, 46 Pages, 2000/11

JAERI-Tech-2000-059.pdf:2.86MB

no abstracts in English

Journal Articles

Divertor biasing effects to reduce L/H power threshold in the JFT-2M tokamak

Miura, Yukitoshi; *; *; Hoshino, Katsumichi; *; *; Kasai, Satoshi; Kawakami, Tomohide; Kawashima, Hisato; Maeda, M.*; et al.

Fusion Energy 1996, p.167 - 175, 1997/05

no abstracts in English

Journal Articles

Investigation of causality in the H-L transition on the JFT-2M tokamak

*; *; *; *; *; *; *; Oikawa, Toshihiro; *; *; et al.

Fusion Energy 1996, p.885 - 890, 1997/05

no abstracts in English

JAEA Reports

Calibration of plutonium accountancy tanks at NUCEF critical facility; Calibration under tank ventilation

Mineo, Hideaki; Yanagisawa, Hiroshi; Tonoike, Kotaro; ; Hirose, Hideyuki; Murakami, Kiyonobu; *; Dojiri, Shigeru; Takeshita, Isao

JAERI-Tech 96-027, 209 Pages, 1996/06

JAERI-Tech-96-027.pdf:7.69MB

no abstracts in English

Journal Articles

Present status of nuclear criticality safety research; Highlights of ICNC'95, the 5th International Conference on Nuclear Criticality Safety

Nishina, Kojiro*; *; Miyoshi, Yoshinori; Suzaki, Takenori; Okuno, Hiroshi; Nomura, Yasushi; Mitake, Susumu*; ; Tonoike, Kotaro; *; et al.

Nihon Genshiryoku Gakkai-Shi, 38(4), p.262 - 271, 1996/00

no abstracts in English

Journal Articles

Measurement and analysis on initial tank calibration at NUCEF

Yanagisawa, Hiroshi; Mineo, Hideaki; Tonoike, Kotaro; Takeshita, Isao; *

Journal of Nuclear Materials Management, 23, p.959 - 964, 1995/00

no abstracts in English

JAEA Reports

Initial tank calibration at NUCEF critical facility, 1; Measurement procedure and its result

Yanagisawa, Hiroshi; Mineo, Hideaki; *; Tonoike, Kotaro; *; Takeshita, Isao

JAERI-Tech 94-001, 242 Pages, 1994/07

JAERI-Tech-94-001.pdf:9.01MB

no abstracts in English

Journal Articles

Construction of Fracture Database System and its Application to Rock Mass Characterization

Noguchi, Yoshifumi*; Iwasaki, Hiroshi*; Kaneko, Katsuhiko*; Koike, Katsuaki*

Joho Chishitsu, 4(2), p.45 - 57, 1993/00

Journal Articles

The Thermal expansion coefficient and Gruneisen parameter of InP crystal low temperatures

Haruna, K.*; Maeta, Hiroshi; Ohashi, K.*; Koike, T.*

J. Phys., C, 20(32), p.5275 - 5279, 1987/11

The thermal expansion of the lattice constante of InP crystal has been measured in the rage 4.2-300 K by the Bond method and teh rsults are shown graphically.

Oral presentation

Function test and critical experiment on uranyl nitrate solution with STACY, 34; Reactivity effect of FP material on heterogeneous core with 1.5 cm lattice pitch

Watanabe, Shoichi; Tonoike, Kotaro; Yoshiyama, Hiroshi; Yamamoto, Toshihiro; Izawa, Kazuhiko; Miyoshi, Yoshinori

no journal, , 

no abstracts in English

Oral presentation

Electroic states at the interface of Fe/MgO magnetic tunneling junction

Sakurai, Hiroshi*; Tamura, Takuro*; Kurachi, Toshitaka*; Homma, Satoshi*; Oike, Hiromi*; Agui, Akane; Sakurai, Yoshiharu*; Ito, Masayoshi*; Adachi, Hiromichi*; Kawata, Hiroshi*

no journal, , 

no abstracts in English

Oral presentation

Evaluation of errors in applying MVP/JENDL-3.2 to criticality calculations of heterogeneous uranium fuel systems

Okuno, Hiroshi; Tonoike, Kotaro; Kawasaki, Hiromitsu*

no journal, , 

no abstracts in English

Oral presentation

High linear power irradiation test with Am-MOX fuels, 7; Evaluation of the thermal design aspect for FBR MOX fuels

Ikusawa, Yoshihisa; Kikuchi, Keiichi; Ozawa, Takayuki; Maeda, Seiichiro; Nakajima, Hiroshi*; Koike, Naoto

no journal, , 

To study the thermal performance of Am-MOX fuels, the high linear power irradiation test with Am-MOX fuels "B14 irradiation test" was carried out in the fast experimental reactor "JOYO". From the result of the irradiation test, the thermal performance for Am-MOX fuel was confirmed and the fuel irradiation behavior code was verified.

28 (Records 1-20 displayed on this page)