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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.
Yokoyama, Kenji; Hirai, Yasushi*; Tatsumi, Masahiro*
JAEA-Data/Code 2010-015, 218 Pages, 2010/11
JAEA-Data-Code-2010-015.pdf:49.32MB
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, functionalities for debugging have been enhanced by preparing an error handling mechanism in order to provide higher level of usability for users of the framework. Other functionalities have been also developed to deal with complex calculation routes with corrections such as analysis of critical experiments by introducing a mechanism for flexible handling of computational procedures.
Yokoyama, Kenji; Hirai, Yasushi*; Tatsumi, Masahiro*
JAEA-Data/Code 2010-016, 92 Pages, 2010/10
JAEA-Data-Code-2010-016.pdf:12.22MB
Development of burnup analysis system for fast reactors with modularity and flexibility is being done that would contribute to actual core design work and improvement of prediction accuracy. In this fiscal year the present study, by extending the prototype system, features for handling of control rods and energy collapse of group constants have been designed and implemented. In addition, a mechanism for database management has been developed by extending the idea on restart files in order to help user easily access arbitrary data of the results.
Yokoyama, Kenji; Hirai, Yasushi*; Hyodo, Hideaki*; Tatsumi, Masahiro*
JAEA-Data/Code 2009-016, 100 Pages, 2010/02
JAEA-Data-Code-2009-016.pdf:8.18MB
Development of burnup analysis system for fast reactors with modularity and flexibility is being done that would contribute to actual core design work and improvement of prediction accuracy. In the present study, we implemented functions for cell calculations and burnup calculations. With this, whole steps in analysis can be carried out with only this system. In addition, we modified the specification of user input to improve the convenience of this system. Since implementations being done so far had some bottlenecks to be resolved; we have realized the improvement on efficiency and amount of memory usage with modification on actual implementation.
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.
Hirai, Yasushi*; Hyodo, Hideaki*; Tatsumi, Masahiro*; Yokoyama, Kenji
JAEA-Data/Code 2008-021, 110 Pages, 2008/10
JAEA-Data-Code-2008-021.pdf:3.47MB
Development of burnup analysis system for fast reactors with modularity and flexibility is being done that would contribute to actual core design work and improvement of prediction accuracy. In the previous study on "Development of Burnup Analysis System for Fast Reactors (2)" in FY2006, design and implementation of models for detailed geometry of assembly, fuel loading pattern and so on, accompanied with specification and implementation of input file handling to construct data models. In this study, a prototype system has been implemented in which functionalities are embedded for calculation of macroscopic cross section, core calculation and burnup calculation applying the fruits of the study "Development of a Framework for the Neutronics Analysis System for Next Generation (2)". It also implements a fuel reloading/shuffling function controlled with simple description in user input for multi-cycle burnup analysis.
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.
Yokoyama, Kenji; Hirai, Yasushi*; Tatsumi, Masahiro*; Hyodo, Hideaki*; Chiba, Go; Hazama, Taira; Nagaya, Yasunobu; Ishikawa, Makoto
Proceedings of International Conference on the Physics of Reactors, Nuclear Power; A Sustainable Resource (PHYSOR 2008) (CD-ROM), 8 Pages, 2008/09
A development project of the next generation neutronics analysis code system, MARBLE, has been launched in JAEA. A software platform and common data models for fast reactor neutronics analysis were developed to realize the new system. At present, a fast reactor burnup calculation system, ORPHEUS, has been implemented in the MARBLE system. The new system reproduced benchmark results by the conventional code system and it reduced input data preparation works with the help of the capabilities supported by common data model packages. The new system was validated in an analysis of a burnup reactivity coefficient measured in the experimental fast reactor JOYO. These results show that MARBLE/ORPHEUS can be adopted as a new standard neutronics analysis system for fast reactors.
Tatsumi, Masahiro*; Yokoyama, Kenji
JAEA-Data/Code 2007-020, 106 Pages, 2007/11
JAEA-Data-Code-2007-020.pdf:17.99MB
JAEA has been promoting the development of innovative analysis methods and models for next-generation nuclear reactor systems; advanced analysis system has been developing to apply the object-oriented approach in order to reflect such the latest methods and models to basic designs and operations of reactors in the efficient and effective way. The developing system adopt the two-layer model which consists of a control layer written in the Python and a solver layer in the C++. The principle on the two-layer model was examined followed by the design and implementation of a library that enabled transparent transfer of data models between the two layers. In each layer, appropriate numerical library was used for better performance. In the present library, a model proxy was implemented to exchange internal data that is represented in different ways in each layer. With this mechanism, it confirmed that data exchange between the layers can be performed easily and effectively.
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.
Fukushima, Masami*; Tatsumi, Kenji*; Nagao, Seiya
Environmental Science & Technology, 35(18), p.3683 - 3690, 2001/09
Times Cited Count：135 Percentile：92.77(Engineering, Environmental)no abstracts in English
Yokoyama, Kenji; Ishikawa, Makoto; Tatsumi, Masahiro*; Hyodo, Hideaki*
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Hyodo, Hideaki*; Tatsumi, Masahiro*; Yokoyama, Kenji; Ishikawa, Makoto
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Hirai, Yasushi*; Tatsumi, Masahiro*; Hyodo, Hideaki*; Yokoyama, Kenji; Ishikawa, Makoto
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Yokoyama, Kenji; Tatsumi, Masahiro*; Hirai, Yasushi*; Hyodo, Hideaki*; Numata, Kazuyuki*; Iwai, Takehiko*; Jin, Tomoyuki*; Hazama, Taira; Nagaya, Yasunobu; Chiba, Go; et al.
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Hirai, Yasushi*; Yokoyama, Kenji; Numata, Kazuyuki*; Jin, Tomoyuki*; Tatsumi, Masahiro*; Ishikawa, Makoto
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