Tomohiro Endo

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Associate Professor

Nagoya University

Japan

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About

Tomohiro Endo is an Associate Professor at Nagoya University, Japan. His research encompasses areas such as reactor physics, nuclear data assimilation, and transport calculations, as reflected in his recent publications. Notable works include advancements in fine spatial mesh kinetics simulation, absolute measurements of reactor subcriticality, and the development of improved methodologies for power distribution reconstruction in high-temperature gas-cooled reactors.

Recent Grants

Grant: Close

Improvement of prediction accuracy of advanced reactors: Precise and robust cross section adjustment method based on active subspace approach

Open Date: 2021-04-01

Close Date: 2024-03-31

Grant: Close

Development of subcritical measurement technique for unknown systems

Open Date: 2019-04-01

Close Date: 2022-03-01

Grant: Close

Development of subcritical measurement technique for unknown systems

Open Date: 2019-04-01

Close Date: 2022-03-31

Grant: Close

Estimation of statistical error of probability table using bootstrap method

Open Date: 2018-04-01

Close Date: 2022-03-31

Grant: Close

Estimation of statistical error of probability table using bootstrap method

Open Date: 2018-04-01

Close Date: 2022-03-31

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2023

Collaborators (4)

Akio Yamamoto

Nagoya University

JAPAN

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Kengo Hashimoto

Professor

Kindai University

JAPAN

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Genichiro Wakabayashi

professor

Kindai University

JAPAN

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Kosuke Tsujita

Senior Assistant Professor

University of Fukui

JAPAN

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Tomohiro Endo

Research Interests

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About

Recent Grants

Articles (25)

Sub-pin level distribution tallies and statistical error estimation with POD tallies in two-dimensional C5G7 benchmark

Ikaros3D: a real-time 3D fine spatial mesh kinetics simulator using POD

Absolute measurement of subcriticality in dollar units based on lag-1 autocovariance of zero-power reactor noise

Verification of in-core power distribution reconstruction based on POD for high-temperature gas-cooled reactors using ex-core detectors

A deterministic transport calculation method of α-eigenvalue for non-multiplying system using framework of k-eigenvalue calculation

Hybrid data assimilation methods for nuclear-data-induced uncertainties

Treatment of corner crossing ray-traces in CMFD acceleration of MOC

Reduced order SP 3 core calculation based on local/global iterations using proper orthogonal decomposition

Impact of nuclear data updates from JENDL-4.0 to JENDL-5 on burnup calculations of light-water reactor fuels

Simplified Treatment of Coating Layers in TRISO Fuel in Statistical Geometry Method in Monte Carlo Calculation

Development of Multigroup Monte Carlo Neutron Transport Method with Regionwise Even-Parity Discontinuity Factor

Flux distribution tallies using proper orthogonal decomposition in Monte Carlo calculations

Development of nuclear data processing code FRENDY version 2

Impact of Uncertainty Reduction on Lead-Bismuth Coolant in Accelerator-Driven System Using Sample Reactivity Experiments

Limited linear source approximation with edge detection for convergence stability of method of characteristics

A Feynman-α analysis ranging over time constants of delayed neutrons based on time-sequence counting data consecutively acquired for a very long time

Uncertainty reduction of sodium void reactivity using data from a sodium shielding experiment

Deterministic Transport Calculation Method for Statistical Geometry with Small Fuel Particles

Deterministic sampling method using simplex ensemble and scaling method for efficient and robust uncertainty quantification

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

Sensitivity analysis of risk assessment for continuous Markov process Monte Carlo method using correlated sampling method

Development of ACE file perturbation tool using FRENDY

An estimation method for an unknown covariance in cross-section adjustment based on unbiased and consistent estimator

Impact of nuclear data revised from JENDL-4.0 to JENDL-5 on PWR spent fuel nuclide composition

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

Collaborators (4)

Akio Yamamoto

Kengo Hashimoto

Genichiro Wakabayashi

Kosuke Tsujita

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