研究者詳細 - 遠藤　知弘

MISC - 遠藤　知弘

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Correction Technique for Coarse Group Cross Sections Considering Spectral Interference Effect on Pin-by-Pin BWR Core Analysis 査読有り国際誌

T. Fujita, T. Endo, A. Yamamoto

Proc. Int. Congress on Advances in Nuclear Power Plants (ICAPP2013) 頁： 936 - 945 2013年4月

Correction of Spectral Interference Effect on Pin-by-Pin BWR Core Analysis 査読有り国際誌

T. Fujita, T. Endo, A. Yamamoto

Trans. Am. Nucl. Soc.107 巻頁： 1141 - 1143 2012年11月

Subcriticality Measurement by Neutron Source Multiplication Method with Detected-Neutron Multiplication Factor 査読有り国際誌

T. Endo, A. Yamamoto, C.H. Pyeon, T. Yagi

Trans. Am. Nucl. Soc.107 巻頁： 648 - 651 2012年11月

Efficient Calculation Scheme with Preservation of Transmission Probabilities in the Method of Characteristics 査読有り国際誌

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

Trans. Am. Nucl. Soc.107 巻頁： 1105 - 1107 2012年11月

記述言語：英語掲載種別：研究発表ペーパー・要旨（国際会議）出版者・発行元：American Nuclear Society

In this study, an efficient calculation scheme for MOC is investigated. The equation for the effective length of a path line is derived based on an assumption that the lengths are linearly distributed in a strip. By using the effective length, the transmission probabilities in each strip can be preserved. Through the verification calculations, the accuracy of the present method can be confirmed, and efficiency of the MOC calculation is expected to be improved by the present method.

Higher Order Treatment on Temporal Derivative of Angular Flux for Time-Dependent MOC 査読有り国際誌

K. Tsujita, T. Endo, A. Yamamoto, Y. Kamiyama, K. Kirimura

Trans. Am. Nucl. Soc.107 巻頁： 1101 - 1104 2012年11月

Kinetic Calculation Method in Space-Time Frame Using Characteristic Line 査読有り国際誌

K. Tsujita, T. Endo, A. Yamamoto

Trans. Am. Nucl. Soc.106 巻頁： 743 - 746 2012年6月

Analysis of Erbia-loaded Critical Experiments in KUCA using AEGIS Cross Section Library 査読有り国際誌

A. Yamamoto, T. Endo, X. Wu

Trans. Am. Nucl. Soc.106 巻頁： 715 - 718 2012年6月

Estimation of Average Burnup of Damaged Fuels Loaded in Fukushima Dai-ichi Reactors by using the Cs134/Cs137 Ratio Method 査読有り国際誌

T. Endo, S. Sato, A. Yamamoto

Proc. Physor2012 - Advanced in Reactor Physics - Linking research, Industry and Education 頁： 3246 - 3253 2012年4月

担当区分：筆頭著者,　責任著者記述言語：英語掲載種別：研究発表ペーパー・要旨（国際会議）

Cs134/Cs137 ratio method for measured radioactivities of 134Cs and 137Cs in contaminated soils within the range of 100 km from the Fukushima Dai-ichi nuclear power plants. As a result, the measured Cs134/Cs137 ratio from the contaminated soil is 0.996±0.07 as of March 11th, 2011. Based on the Cs134/Cs137 ratio method, the estimated burnup of damaged fuels is approximately 17.2±1.5 [GWd/tHM]. It is noted that the numerical results of various calculation codes (SRAC2006/PIJ, SCALE6.0/TRITON, and MVP-BURN) are almost the same evaluation values of Cs134/Cs137 ratio with same evaluated nuclear data library (ENDF-B/VII.0). The void fraction effect in depletion calculation has a major impact on 134Cs/137Cs ratio compared with the differences between JENDL-4.0 and ENDF-B/VII.0.

Uncertainty Estimation of Core Safety Parameters using Cross-Correlations of Covariance Matrix 査読有り国際誌

A. Yamamoto, Y. Yasue, T. Endo, Y. Kodama, Y. Ohoka, M. Tatsumi

Proc. Physor2012 - Advanced in Reactor Physics - Linking research, Industry and Education 頁： 2880 - 2895 2012年4月

記述言語：英語掲載種別：研究発表ペーパー・要旨（国際会議）

An uncertainty estimation method for core safety parameters, for which measurement values are not obtained, is proposed. We empirically recognize the correlations among the prediction errors among core safety parameters, e.g., a correlation between the control rod worth and assembly relative power of corresponding position. Correlations of uncertainties among core safety parameters are theoretically estimated using the covariance of cross sections and sensitivity coefficients for core parameters. The estimated correlations among core safety parameters are verified through the direct Monte-Carlo sampling method. Once the correlation of uncertainties among core safety parameters is known, we can estimate the uncertainty of a safety parameter for which measurement value is not obtained. Furthermore, the correlations can be also used for the reduction of uncertainties of core safety parameters.

Development of a Lattice Physics Code for Sensitivity Analysis Based on Generalized Perturbation Theory 査読有り国際誌

S. Kato, T. Endo, A. Yamamoto, Y. Kimura

Trans. Am. Nucl. Soc.105 巻頁： 851 - 854 2011年10月

Assembly Discontinuity Factor for Angular Flux in Transport Calculation 査読有り国際誌

A. Yamamoto, T. Endo

Trans. Am. Nucl. Soc.105 巻頁： 862 - 864 2011年10月

Evaluation of Correlations among Uncertainties of Core Neutronic Parameters in Infinite Slab Geometry 査読有り国際誌

Y. Yasue, T. Endo, A. Yamamoto, Y. Kodama, Y. Ohoka, M. Tatsumi

Trans. Am. Nucl. Soc.105 巻頁： 486 - 488 2011年10月

A Unified Numerical Algorithm for Space-Dependent Kinetic Equation 招待有り査読有り国際誌

T. Endo, Y. Ban, A. Yamamoto

Trans. Am. Nucl. Soc.104 巻頁： 865 - 867 2011年6月

A Derivation of Discontinuity Factor for Angular Flux in Integro-Differential Transport Equation 査読有り国際誌

A. Yamamoto, T. Endo, Y. A. Chao

Trans. Am. Nucl. Soc.104 巻頁： 815 - 817 2011年6月

Search Strategy of Detector Position for Neutron Source Multiplication Method by using Detected-Neutron Multiplication Factor 招待有り国際誌

T. Endo

Transactions of Korean Nuclear Society 2011 Spring Meeting 頁： 131 - 132 2011年5月

担当区分：筆頭著者,　責任著者記述言語：英語掲載種別：研究発表ペーパー・要旨（国際会議）出版者・発行元：Korean Nuclear Society

In this paper, based on the idea of kdet, it is clear that correlation factors of the NSM method consist of the sourc-flux correction factor fs to fix the difference of non-fission component of neutron count rate, and the conversion factor fc to convert from kdet to the effective multiplication factor keff. Through the numerical analysis of three-dimensional two-group transport calculations for simple geometry, appropriate detector positions where kdet=keff could be find out for only one certain subcritical state, e.g., the reference state. By putting a neutron detector at such a particular position, the target neutron multiplication factors can be well estimated even without any corrections.

Effect of Uncertainty of Planned Cycle Length in Multicycle Fuel Optimization 査読有り国際誌

K. Ohori, T. Endo, A. Yamamoto

Trans. Am. Nucl. Soc.103 巻頁： 707 - 710 2010年11月

Incorporation of Two-Term Rational Approximation in Tone Method for Resonance Calculation 査読有り国際誌

A. Yamamoto, T. Endo, G. Chiba

Trans. Am. Nucl. Soc.103 巻頁： 711 - 713 2010年11月

Investigation of Theoretical Approach to Establish Energy Group Structure for BWR Pin-by-Pin Core Analysis 査読有り国際誌

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

Trans. Am. Nucl. Soc.103 巻頁： 721 - 723 2010年11月

Verification and validation of AEGIS/SCOPE2 the state-of-the-art in-core fuel management system for PWRs 査読有り国際誌

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

Proc. 18th International Conference on Nuclear Engineering2 巻頁： 9 - 15 2010年5月

記述言語：英語掲載種別：研究発表ペーパー・要旨（国際会議）

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 査読有り国際誌

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

Proc. International Conference on the Physics of Reactors (Physor2010) 頁： 951 - 962 2010年5月

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