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Numerical benchmark problem of solid-moderated enriched-uranium-loaded core at Kyoto university critical assembly

Journal of nuclear science and technology, 2020-02, Vol.57 (2), p.187-195

2020

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Applicability evaluation of Akaike’s Bayesian information criterion to covariance modeling in the cross-section adjustment method

EPJ Web of Conferences, 2023, Vol.281, p.8

2023

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Introduction to Nuclear Reactor Experiments

1st Edition 2023, 2023

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Uncertainty and regression analysis of the MSLB accident in PWR based on unscented transformation and low rank approximation

Annals of nuclear energy, 2020-08, Vol.143, p.107493, Article 107493

2020

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Development of a robust nuclear data adjustment method to outliers

EPJ Web of Conferences, 2023, Vol.281, p.6

2023

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Kangaroo mother care alters chromogranin A and perfusion index in preterm babies

Pediatrics international, 2021-01, Vol.63 (1), p.53-59

2021

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Applicability of Dynamic Mode Decomposition to Estimate Fundamental Mode Component of Prompt Neutron Decay Constant from Experimental Data

Nuclear science and engineering, 2022-02, Vol.196 (2), p.133-143

2022

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Theoretical Derivation of a Unique Combination Number Hidden in the Higher-Order Neutron Correlation Factors Using the Pál-Bell Equation

Nuclear science and engineering, 2023-02, Vol.197 (2), p.176-188

2023

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Confidence interval estimation by bootstrap method for uncertainty quantification using random sampling method

Journal of nuclear science and technology, 2015-08, Vol.52 (7-8), p.993-999

2015

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ESTIMATED CRITICALITY LOWER-LIMIT MULTIPLICATION FACTOR OF LOW-ENRICHED URANIUM DIOXIDE-CONCRETE SYSTEM USING THE BOOTSTRAP METHOD

EPJ Web of conferences, 2021, Vol.247, p.17001

2021

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Utilization of Regionwise Even-Parity Discontinuity Factor to Reduce Discretization Error of MOC

Nuclear science and engineering, 2019-03, Vol.193 (3), p.253-268

2019

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Investigation of Discoloration of Furosemide Tablets in a Light-Shielded Environment

Chemical and Pharmaceutical Bulletin, 2017/04/01, Vol.65(4), pp.373-380

2017

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Flux Region Assignment Method Using Ray Trace Information for the Method of Characteristics to Improve Cache Efficiency

Nuclear science and engineering, 2018-12, Vol.192 (3), p.240-253

2018

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Bias factor method using random sampling technique

Journal of nuclear science and technology, 2016-10, Vol.53 (10), p.1494-1501

2016

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Nuclear data-induced uncertainty quantification of prompt neutron decay constant based on perturbation theory for ADS experiments at KUCA

Journal of nuclear science and technology, 2020-02, Vol.57 (2), p.196-204

2020

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EXPERIMENT OF UNIQUE COMBINATION NUMBER DUE TO THE THIRD-ORDER NEUTRON-CORRELATION

EPJ Web of conferences, 2021, Vol.247, p.9004

2021

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Recent developments in the GENESIS code based on the Legendre polynomial expansion of angular flux method

Nuclear Engineering and Technology, 2017, 49(6), , pp.1143-1156

2017

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Application of neutron current method for Dancoff factor estimation of fuel particles in double-heterogeneous fuel

Journal of nuclear science and technology, 2024-03, Vol.61 (3), p.354-362

2024

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Experimental analysis and uncertainty quantification using random sampling technique for ADS experiments at KUCA

Journal of nuclear science and technology, 2018-04, Vol.55 (4), p.450-459

2018

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Neutron Generation Time in Highly-Enriched Uranium Core at Kyoto University Critical Assembly

Nuclear science and engineering, 2020-12, Vol.ahead-of-print (ahead-of-print), p.1-12

2020

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Uncertainty Quantification of LWR Core Characteristics Using Random Sampling Method

Nuclear science and engineering, 2015-10, Vol.181 (2), p.160-174

2015

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Estimation of sensitivity coefficients of core characteristics based on reduced-order modeling using sensitivity matrix of assembly characteristics

Journal of nuclear science and technology, 2017-06, Vol.54 (6), p.637-647

2017

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Convergence behavior of statistical uncertainty in probability table for cross section in unresolved resonance region

Journal of nuclear science and technology, 2023-11, Vol.60 (11), p.1397-1405

2023

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Benchmarks of subcriticality in accelerator-driven system at Kyoto University Critical Assembly

Nuclear Engineering and Technology, 2017, 49(6), , pp.1234-1239

2017

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A unified approach for numerical calculation of space-dependent kinetic equation

Journal of nuclear science and technology, 2012-05, Vol.49 (5), p.496-515

2012

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Numerical benchmark problem of solid-moderated enriched-uranium-loaded core at Kyoto university critical assembly

Applicability evaluation of Akaike’s Bayesian information criterion to covariance modeling in the cross-section adjustment method

Introduction to Nuclear Reactor Experiments

Uncertainty and regression analysis of the MSLB accident in PWR based on unscented transformation and low rank approximation

Development of a robust nuclear data adjustment method to outliers

Kangaroo mother care alters chromogranin A and perfusion index in preterm babies

Applicability of Dynamic Mode Decomposition to Estimate Fundamental Mode Component of Prompt Neutron Decay Constant from Experimental Data

Theoretical Derivation of a Unique Combination Number Hidden in the Higher-Order Neutron Correlation Factors Using the Pál-Bell Equation

Confidence interval estimation by bootstrap method for uncertainty quantification using random sampling method

ESTIMATED CRITICALITY LOWER-LIMIT MULTIPLICATION FACTOR OF LOW-ENRICHED URANIUM DIOXIDE-CONCRETE SYSTEM USING THE BOOTSTRAP METHOD

Utilization of Regionwise Even-Parity Discontinuity Factor to Reduce Discretization Error of MOC

Investigation of Discoloration of Furosemide Tablets in a Light-Shielded Environment

Flux Region Assignment Method Using Ray Trace Information for the Method of Characteristics to Improve Cache Efficiency

Bias factor method using random sampling technique

Nuclear data-induced uncertainty quantification of prompt neutron decay constant based on perturbation theory for ADS experiments at KUCA

EXPERIMENT OF UNIQUE COMBINATION NUMBER DUE TO THE THIRD-ORDER NEUTRON-CORRELATION

Recent developments in the GENESIS code based on the Legendre polynomial expansion of angular flux method

Application of neutron current method for Dancoff factor estimation of fuel particles in double-heterogeneous fuel

Experimental analysis and uncertainty quantification using random sampling technique for ADS experiments at KUCA

Neutron Generation Time in Highly-Enriched Uranium Core at Kyoto University Critical Assembly

Uncertainty Quantification of LWR Core Characteristics Using Random Sampling Method

Estimation of sensitivity coefficients of core characteristics based on reduced-order modeling using sensitivity matrix of assembly characteristics

Convergence behavior of statistical uncertainty in probability table for cross section in unresolved resonance region

Benchmarks of subcriticality in accelerator-driven system at Kyoto University Critical Assembly

A unified approach for numerical calculation of space-dependent kinetic equation

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