Faculty Profiles - ENDO Tomohiro

MISC - ENDO Tomohiro

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Incorporation of Two-Term Rational Approximation in Tone Method for Resonance Calculation Reviewed International journal

A. Yamamoto, T. Endo, G. Chiba

Trans. Am. Nucl. Soc. Vol. 103 page： 711 - 713 2010.11

Investigation of Theoretical Approach to Establish Energy Group Structure for BWR Pin-by-Pin Core Analysis Reviewed International journal

T. Fujita, K. Otsuka, K. Tada, T. Endo, A. Yamamoto, S. Kosaka, G. Hirano

Trans. Am. Nucl. Soc. Vol. 103 page： 721 - 723 2010.11

Verification and validation of AEGIS/SCOPE2 the state-of-the-art in-core fuel management system for PWRs Reviewed International journal

Masahiro Tatsumi, Yasunori Ohoka, Tomohiro Endo, Naoki Sugimura, Masato Tabuchi, Hideaki Hyoudou, Tadashi Ushio, Masaaki Mori, Akio Yamamoto

Proc. 18th International Conference on Nuclear Engineering Vol. 2 page： 9 - 15 2010.5

Language：English Publishing type：Research paper, summary (international conference)

Verification and validation of AEGIS/SCOPE2, a state-of-the-art in-core fuel management system for PWRs, was conducted. Verification of implementations for processes of tabulation and reconstruction of cross sections data in the system was confirmed through benchmark problems to confirm consistency between AEGIS and SCOPE2 in terms of reactivity and pin power distribution with identical computational condition in single- and multi-assembly geometry. In validation study numerical performance of the system was demonstrated in analyses of the B&amp
W's critical experiment and tracking calculations for commercial PWRs in combination of ENDF/B-VII.0 library. It is found the present system gives stability in prediction of critical boron concentration and radial power distribution. Copyright © 2010 by ASME.

DOI： 10.1115/ICONE18-29154

Scopus

Numerical Solution of Reactor Kinetics Equation with Krylov Subspace Method for Matrix Exponential Reviewed International journal

Y. Ban, A. Yamamoto, Y. Yamane, T. Endo

Proc. International Conference on the Physics of Reactors (Physor2010) page： 951 - 962 2010.5

Critical Experiments in Kyoto University Critical Assembly for Development of >5wt% Enrichment Erbia Bearing Super High Burnup Fuel Reviewed International journal

T. Endo, M. Yamasaki, T. Kuroishi

Proc. Nuclear Criticality Safety Division Topical Meeting on Realism, Robustness and the Nuclear Renaissance (NCSD 2009) page： 536 - 545 2009.9

Authorship：Lead author,　Corresponding author Language：English Publishing type：Research paper, summary (international conference)

In order to improve fuel cycle economics with securing critical safety, the development project on Erbia bearing Super High Burnup (Er-SHB) fuel with >5wt% uranium enrichment is in progress. In this project, a series of critical experiments of erbia loaded core have been performed at Kyoto University Critical Assembly (KUCA). In order to accumulate experimental data under various conditions, four erbia loaded critical cores have been constructed by changing averaged enrichment, erbia content, and H/U-235 ratio. Several experimental data such as criticality and erbia sample worth have been measured. In this paper, we will show the numerical analyses by using probabilistic and deterministic methods. As a result, the C/E values are evaluated by the Monte Carlo method can be predicted within 0.998-1.004, thus the prediction accuracy of criticality for erbia loaded core is validated. For the erbia sample worth evaluated by the deterministic code, it could be generally concluded that significant discrepancy between calculation and measurement could not be observed. However, further study such as the treatment of heterogeneous effects in the fuel elements will be necessary to finalize the C/E values.

Study on Kinetic Transport Solvers for Pin-by-Pin Core Calculation Reviewed International journal

T. Endo, M. Tatsumi

Proc. International Conference on the Physics of Reactors (Physor2008) page： 981 - 987 2008.9

Authorship：Lead author,　Corresponding author Language：English Publishing type：Research paper, summary (international conference)

SCOPE2 is an advanced core calculation code to solve the multi-group SP3 transport equations within three-dimensional pin-by-pin geometry. For the purpose of wider range of applicability such as analysis for dynamic rod worth measurements, widely known kinetic solvers have been implemented in SCOPE2. The implemented solvers are the backward Euler, the theta, and the frequency-transform method. In implementing the theta method in SCOPE2, an automatic determination of weighting parameter is adopted in order to obtain stable solutions with as high accuracy as possible. In the frequency-transform method, the space- and energy dependant frequency is estimated to reduce the discretization error of transformed neutron flux. Through an analysis of the 3-D LMW benchmark problem without thermal hydraulic feedback, it was demonstrated that the kinetic solvers are correctly implemented in SCOPE2, and the accuracy of each solver was verified.

Yet Another Optimum Polar Angle Quadrature Set for the Method of Characteristics Reviewed International journal

M. Tabuchi, A. Yamamoto, T. Endo, N. Sugimura, T. Ushio, M. Mori

Trans. Am. Nucl. Soc. Vol. 93 page： 506 - 507 2005.11

Medical Isotope Production Using Pressurized Water Reactor Reviewed

T. Endo;A. Yamamoto

Proc. International Symposium on Isotope Science and Engineering from Basic to Applications Vol. CD-ROM 2005.9

Efficient Calculation of Time-Dependent Neutron Transport Equation using the Constrained Interpolated Profile (CIP) Method Reviewed International journal

S. Kano, T. Endo, A. Yamamoto, Y. Yamane, Y. Kitamura

Proc. International topical Meeting on Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications (M&C2005) page： CD-ROM 2005.9

Development of Advanced Neutronics Design System of Next Generation, AEGIS Reviewed International journal

N. Sugimura, T. Ushio, M. Mori, A. Yamamoto, M. Tabuchi, T. Endo

Proc. International topical Meeting on Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications (M&C2005) page： CD-ROM 2005.9

Derivation of the Space and Energy Dependent Formula for the Third Order Neutron Correlation Technique Reviewed International journal

T. Endo, Y. Kitamura, A. Yamamoto, Y. Yamane

Proc. PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments page： 1085 - 1095 2004.4

Authorship：Lead author,　Corresponding author Language：English Publishing type：Research paper, summary (international conference)

We have studied a measurement technique of subcriticality by using the neutron correlation methods. Among various techniques, we have paid attention to the third order neutron correlation technique, which utilizes the third order fluctuations of neutron counts. By using this technique, we can obtain the absolute value of subcriticality without prior knowledge of the prompt neutron decay constant at a reference state. To apply the third order neutron correlation technique to actual experiments, we must consider the effects of the spatial and neutron energy distributions in this technique. For this purpose, we derived the generalized theoretical formulas of the third order neutron correlation technique that took account of the spatial and neutron energy effects.

Absolute Measurement of the Subcriticality Based on the Third Order Neutron Correlation in Consideration of the Finite Nature of Neutron Counts Data Reviewed International journal

T. Endo, Y. Kitamura, Y. Yamane

Proc. the 7th International Conference on Nuclear Criticality Safety ICNC2003; Challenges in the Pursuit of Global Nuclear Criticality Safety page： 215 - 220 2003.10

Authorship：Lead author,　Corresponding author Language：English Publishing type：Research paper, summary (international conference) Publisher：Japan Atomic Energy Agency

We have studied a measurement of subcriticality by using the neutron correlation method. Furuhashi proposed an absolute measurement of subcriticality by using the third order neutron correlation factor X in addition to the second order neutron correlation factor Y. In actual experiments, the number of neutron counts data is not infinity so that we take the effect of the finite nature of the neutron counts data into account. We derived new formulas in consideration of the number of data and verified them.

DOI： 10.11484/jaeri-conf-2003-019

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