Strain-induced crystallization and phase separation used for fabricating a tough and stiff slide-ring solid polymer electrolyte

Hashimoto, Kei*; Shiwaku, Toru*; Aoki, Hiroyuki; Yokoyama, Hideaki*; Mayumi, Koichi*; Ito, Kozo*

Science Advances (Internet), 9(47), p.eadi8505_1 - eadi8505_8, 2023/11

https://doi.org/10.1126/sciadv.adi8505

Can the decision way by the "veil of ignorance" promote public acceptance?; A Hypothetical scenario survey about selecting a candidate site for geological disposal of high level radioactive waste in Japan

Onuma, Susumu*; Hirose, Yukio*; Osawa, Hideaki; Otomo, Shoji*; Yokoyama, Miki*

Nihon Risuku Kenkyu Gakkai Dai-31-Kai Nenji Taikai Koen Rombunshu (USB Flash Drive), 6 Pages, 2018/11

One reason of not being decided a candidate site for geological disposal of high level radioactive waste is that strong opposition occurs once a name of the place where residents live even if they can understand the necessity of the facility. Therefore, we hypothesized that people would accept the decision if they consent the decision way beforehand under the condition everyone can be involved in as a potential interest party (the ignorance of veil). A hypothetical scenario survey was conducted in Japan. The results revealed that the decision way and the decision under the ignorance of veil were likely to be accepted more than the current decision way even if they became candidate site. Moreover, the decision way under the ignorance of veil was evaluated higher procedural fairness, while the current way was low procedural fairness.

Development of the next generation reactor analysis code system, MARBLE

Yokoyama, Kenji; Tatsumi, Masahiro*; Hirai, Yasushi*; Hyodo, Hideaki*; Numata, Kazuyuki*; Iwai, Takehiko*; Jin, Tomoyuki*; Hazama, Taira; Nagaya, Yasunobu; Chiba, Go; et al.

JAEA-Data/Code 2010-030, 148 Pages, 2011/03

JAEA-Data-Code-2010-030.pdf:3.23MB

A next generation reactor analysis code system, MARBLE, has been developed. MARBLE is a successor of the fast reactor neutronics analysis code systems, JOINT-FR and SAGEP-FR (conventional system), which were developed for so-called JUPITER standard analysis methods. MARBLE has the equivalent analysis capability to the conventional system. On the other hand, burnup analysis functionality for power reactors as improved compared with the conventional system. In the development of MARBLE, the object oriented technology was adopted. As a result, MARBLE became an assembly of components for building an analysis code (i.e. framework) but not an independent analysis code system which simply receives input and returns output. Furthermore, MARBLE provides some pre-built analysis code systems such as the fast reactor neutronics analysis code system, SCHEME, which corresponds to the conventional code and the fast reactor burnup analysis code system, ORPHEUS.

Development of a framework for the neutronics analysis system for next generation, 3

Yokoyama, Kenji; Hirai, Yasushi*; Hyodo, Hideaki*; Tatsumi, Masahiro*

JAEA-Data/Code 2009-012, 208 Pages, 2010/02

JAEA-Data-Code-2009-012.pdf:11.28MB

Japan Atomic Energy Agency promotes development of innovative analysis methods and models in fundamental studies for next-generation nuclear reactor systems. In order to efficiently and effectively reflect the latest analysis methods and models to primary design of prototype reactor and/or in-core fuel management for power reactors, a next-generation analysis system MARBLE has been developed. In the present study, we examined in detail the existing design and implementation of ZPPR critical experiment analysis database followed by unification of models within the framework of the next-generation analysis system by extending to various critical experiment analysis. Furthermore, we examined requirements for functions of analysis results correction which is indispensable for critical analysis system, and designed and implemented an analysis system for various critical experiments including ZPPR.

Development of a framework for the neutronics analysis system for next generation, 2 (Contract research)

Hirai, Yasushi*; Hyodo, Hideaki*; Tatsumi, Masahiro*; Jin, Tomoyuki*; Yokoyama, Kenji

JAEA-Data/Code 2008-020, 188 Pages, 2008/10

JAEA-Data-Code-2008-020.pdf:15.06MB

Japan Atomic Energy Agency promotes development of innovative analysis methods and models in fundamental studies for next-generation nuclear reactor systems. In order to efficiently and effectively reflect the latest analysis methods and models to primary design of prototype reactor and/or in-core fuel management for power reactors, a next-generation analysis system MARBLE has been developed. In this study, detailed design of a framework, its implementation and tests are conducted so that a Python system layer can drive calculation codes written in C++ and/or Fortran. It is confirmed that various type of calculation codes such as diffusion, transport and burnup codes can be treated in the same manner on the platform for unified management system for calculation codes with a data exchange mechanism for abstracted data model between the Python and the calculation code layers.

Restructuring of burnup sensitivity analysis code system by using an object-oriented design approach

Yokoyama, Kenji; Ishikawa, Makoto; Tatsumi, Masahiro*; Hyodo, Hideaki*

Proceedings of International Topical Meeting on Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications (M&C 2005) (CD-ROM), 12 Pages, 2005/09

In this work, a new burnup sensitivity analysis code, PSAGEP, has been developed with help from the object-oriented technique and the scripting language Python. It was confirmed they are powerful to support complex numerical calculation procedure for burnup sensitivity analysis. PSAGEP was reborn from the conventional hard-to-use code system as a user-friendly code system which can calculate the sensitivity coefficients of the nuclear characteristics considering burnup effect to cross-section changes based on the generalized perturbation theory.

R&D of the object-integrated code system for fast reactors; Overview and framework of advanced reactor physics analysis system, MARBLE

Yokoyama, Kenji; Ishikawa, Makoto; Tatsumi, Masahiro*; Hyodo, Hideaki*

no journal, , 

no abstracts in English

R&D of the object-integrated code system for fast reactors, 9; Design and implementation of solver management for burnup analysis of fast reactors

Hirai, Yasushi*; Tatsumi, Masahiro*; Hyodo, Hideaki*; Yokoyama, Kenji; Ishikawa, Makoto

no journal, , 

no abstracts in English

Development of prediction technology of two-phase flow dynamics under earthquake acceleration, 29; Response characteristics of a single bubble in horizontal pipe to horizontal oscillation

Kato, Yuki; Yoshida, Hiroyuki; Yokoyama, Ryotaro*; Kanagawa, Tetsuya*; Kaneko, Akiko*; Monji, Hideaki*; Abe, Yutaka*

no journal, , 

no abstracts in English

Public decision based on procedural fairness using the veil of ignorance; A Hypothetical scenario experiment about selecting a candidate site for geological disposal of high-level radioactive waste in Japan

Onuma, Susumu*; Yokoyama, Miki*; Hirose, Yukio*; Osawa, Hideaki; Otomo, Shoji*

no journal, , 

This study demonstrates the significance of "the veil of ignorance" to promote public acceptance of siting a facility for geological disposal of high-level radioactive waste, which fosters procedural fairness. We conduct a hypothetical scenario experiment in Japan and manipulate the decision way setting two conditions; one is present Japanese way that decides by application from municipalities or offer of the Government, the other is a Switzerland way that all regions have possible to be a candidate site starting from blank. The results indicated that respondents in Switzerland way condition accepted more and regarded the process fairer than those in present Japanese way condition. The potential of adopting the idea of "the veil of ignorance" is discussed.