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Hirai, Yasushi; Hyoudou, Hideaki; Tatsumi, Masahiro; Yokoyama, Kenji
Japan Atomic Energy Agency, Tokai, Ibaraki (Japan)2008
Japan Atomic Energy Agency, Tokai, Ibaraki (Japan)2008
AbstractAbstract
[en] Improvement of the prediction accuracy for neutronics property of fast reactor cores is one of the most important study domains in terms of both achievement of high economical plant efficiency based on reasonably advanced designs and increased reliability and safety margins. In the previous study, considerable improvement of the prediction accuracy in neutronics design has been achieved in the development of the unified constants library as a fruit of a series of critical experiments such as JUPITER in application of the reactor constant adjustments. For design of fast reactor cores, however, improvement of not only static properties but also burnup properties is very important. For such purposes, it is necessary to improve the prediction accuracy of burnup properties using actual burnup data of 'JOYO' and 'MONJU', experimental and prototype fast reactors. Recently, study on effective burnup method for minor actinides becomes important theme. However, there is a problem that analysis work tends to become inefficient for lack of functionality suitable for analysis of composition change due to burnup since the conventional analysis system is targeted to critical assembly systems. Therefore 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 the 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 the present 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. (author)
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Oct 2008; 120 p; Also available from JAEA; URL: http://dx.doi.org/10.11484/JAEA-Data-Code-2008-021; 5 refs., 29 figs., 26 tabs.
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