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Featured researches published by Isao Tatewaki.


Journal of Nuclear Science and Technology | 2012

Analysis of fuel pin behavior under slow-ramp type transient overpower condition by using the fuel performance evaluation code ‘FEMAXI-FBR’

Yasushi Tsuboi; Hiroshi Endo; Tomoko Ishizu; Isao Tatewaki; Hiroaki Saito; Hisashi Ninokata

FEMAXI-FBR has been developed as the one module of the core disruptive accident analysis code ‘ASTERIA-FBR’ in order to evaluate the mixed oxide (MOX) fuel performance under steady, transient and accident conditions of fast reactors consistently. On the basis of light water reactor (LWR) fuel performance evaluation code ‘FEMAXI-6’, FEMAXI-FBR develops specific models for the fast reactor fuel performance, such as restructuring, material migration during steady state and transient, melting cavity formation and pressure during accident, so that it can evaluate the fuel failure during accident. The analysis of test pin with slow transient over power test of CABRI-2 program was conducted from steady to transient. The test pin was pre-irradiated and tested under transient overpower with several % P 0/s (P 0: steady state power) of the power rate. Analysis results of the gas release ratio, pin failure time, and fuel melt radius were compared to measured values. The analysis results of the steady and transient performances were also compared with the measured values. The compared performances are gas release ratio, fuel restructuring for steady state and linear power and melt radius at failure during transient. This analysis result reproduces the measured value. It was concluded that FEMAXI-FBR is effective to evaluate fast reactor fuel performances from steady state to accident conditions.


Journal of Nuclear Science and Technology | 2012

Sensitivity analysis of fuel pin failure performance under slow-ramp type transient overpower condition by using a fuel performance analysis code FEMAXI-FBR

Yasushi Tsuboi; Hiroshi Endo; Tomoko Ishizu; Isao Tatewaki; Hiroaki Saito; Hisashi Ninokata

The FEMAXI-FBR is a fuel performance analysis code and has been developed as one module of core disruptive evaluation system, the ASTERIA-FBR. The FEMAXI-FBR has reproduced the failure pin behavior during slow transient overpower. The axial location of pin failure affects the power and reactivity behavior during core disruptive accident, and failure model of which pin failure occurs at upper part of pin is used by reflecting the results of the CABRI-2 test. By using the FEMAXI-FBR, sensitivity analysis of uncertainty of design parameters such as irradiation conditions and fuel fabrication tolerances was performed to clarify the effect on axial location of pin failure during slow transient overpower. The sensitivity analysis showed that the uncertainty of design parameters does not affect the failure location. It suggests that the failure model with which locations of failure occur at upper part of pin can be adopted for core disruptive calculation by taking into consideration of design uncertainties.


International Journal of Quantum Chemistry | 2012

Molecular dynamics approach to sodium–water reaction compensating macroscopic heat and mass flow dynamics for LMFBR safety

Yukio Ugawa; Hiroshi Endo; Yoshihisa Shindo; Isao Tatewaki; Kazuo Haga; Masaaki Inoue


The Proceedings of the International Conference on Nuclear Engineering (ICONE) | 2015

ICONE23-1948 A STUDY ON CHARACTERISTICS OF MOLTEN POOL SLOSHING IN CORE DISRUPTIVE ACCIDENTS OF FAST REACTORS

Isao Tatewaki; Koji Morita; Hiroshi Endo


23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015 | 2015

A study on characteristics of molten pool sloshing in core disruptive accidents of fast reactors

Isao Tatewaki; Koji Morita; Hiroshi Endo


international conference on supercomputing | 2014

Core Disruptive Accident Analysis using ASTERIA-FBR

Tomoko Ishizu; Hiroshi Endo; Toshihisa Yamamoto; Isao Tatewaki


international conference on supercomputing | 2014

The Specific Bias in Dynamic Monte Carlo Simulations of Nuclear Reactor

Toshihisa Yamamoto; Hiroshi Endo; Tomoko Ishizu; Isao Tatewaki


Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems | 2012

Improvement of the Fast Breeder Reactor Plant Dynamic Analysis Code ADYTUM

Isao Tatewaki; Hiroshi Endo; Tomoko Ishizu; Yoshihisa Shindo


Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE | 2011

ICONE19-44130 DEVELOPMENT OF THE FAST BREEDER REACTOR PLANT DYNAMIC ANALYSIS CODE, ADYTUM

Isao Tatewaki; Yoshihisa Shindo; Tomoko Ishizu; Hiroshi Endo; Hisashi Ninokata


Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE | 2011

ICONE19-43851 CHARACTERISTICS OF FISSION PRODUCTS BEHAVIOR ON A SEVERE ACCIDENT IN FAST BREEDER REACTOR

Masaaki Inoue; Hiroshi Endo; Kazuo Haga; Isao Tatewaki; Kenichiro Sugiyama

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Tomoko Ishizu

Tokyo Institute of Technology

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Hisashi Ninokata

Tokyo Institute of Technology

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Yasushi Tsuboi

Tokyo Institute of Technology

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