Satoshi Takeda

Core optimization method using improved HHO with MLP-based screening for minor actinide transmutation in fast reactors

Chikara Kawasaki, T Kitada, Satoshi Takeda

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Data assimilation with process data from plant simulator experiments focused on PIFs

Tomonori SAKAMAKI, Satoshi Takeda, Takanori Kitada

This study investigates the effectiveness of data assimilation focused on Performance Influence Factors (PIFs) by using process data obtained from plant simulator experiments. Modern Human Reliability Analysis (HRA) methods such as IDHEAS-G incorporate PIF impact into Human Error Probability (HEP) estimation, but …

A Safety Enhanced Core Concept for Metal-Fuel Sodium-Cooled Fast Reactors

Sho Fuchita, Koji Fujimura, Kazuhiro Fujimata, Hirotaka NAKAHARA et autres

A safety enhanced metal fuel core has been developed that prevents fuel pin failure and coolant boiling during unprotected loss of flow (ULOF), unprotected transient over power (UTOP) and unprotected loss of heat sink (ULOHS) without relying on radial expansion reactivity.Specifically, we …

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Oral Semaglutide in an East Asian Population With Overweight or Obesity, With or Without Type 2 Diabetes

Takashi Kadowaki, Line Dam Heftdal, Hae‐Jin Ko, Maria Overvad et autres

Importance: The efficacy and safety of oral semaglutide, 50 mg, in an East Asian population that also includes individuals with type 2 diabetes (T2D), who are prone to weight-related complications at lower body mass index (BMI; calculated as weight in kilograms divided …

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Collapsed energy group structure for analysis of prismatic high-temperature gas-cooled reactor with uranium fuel

Satoshi Takeda, Takanori Kitada, Akio Yamamoto, Kazuya Yamaji et autres

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Investigation of Thermal Cutoff Energy for Accurate Analysis of High-Temperature Engineering Test Reactor

Satoshi Takeda, Takanori Kitada, Akio Yamamoto, Kazuya Yamaji et autres

Abstract This study investigates the appropriate thermal cutoff energy for neutron transport calculations in the High-Temperature Engineering Test Reactor (HTTR). Using the Monte Carlo calculation code mvp3.0, the impact of changing thermal cutoff energy on the multiplication factor was evaluated for the …

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Uniform Thermal Expansion Reactivity Evaluation Based on Reactivity Coefficient for Sodium-Cooled Fast Reactor

Satoshi Takeda, Takanori Kitada, Takafumi Okita, Eiji Hoashi

Abstract This paper presents a method for calculating reactivity changes caused by uniform thermal expansion in sodium-cooled fast reactors using reactivity coefficients. The reactivity changes due to both Z-axis and radial expansion are separated into two effects: the shape change effect and …

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Resonance Treatment of Double-Heterogeneous Fuel Using a Deterministic Statistical Geometry Method in Heterogeneous Transport Calculation Code GALAXY-Z

Kazuya Yamaji, Hiroki Koike, Koji Asano, Satoshi Takeda et autres

A resonance calculation using a deterministic statistical geometry (DSTG) method has been developed to efficiently treat the double heterogeneity of coated fuel particles loaded in a high-temperature gas-cooled reactor. Using the DSTG method, neutron flux spatial distribution can be calculated in a …

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Uncertainty quantification of criticality in light-water-moderated and graphite-reflected core with highly enriched uranium fuel at University Teaching and Research Reactor

Hiroshi Shiga, Kenichi Watanabe, Satoshi Takeda, Genichiro Wakabayashi et autres

Neutronics characteristics are examined by the MCNP6.2 code with ENDF/B-VII.1 for a light-water-moderated and graphite-reflected core with highly enriched uranium fuel at the University Teaching and Research Reactor in Kindai University (UTR-KINKI), demonstrating the meaningful degree of computational accuracies of the criticality, …

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

Akio Yamamoto, Tomohiro Endo, Satoshi Takeda, Kazuya Yamaji et autres

An improved sampling method for flight distance is proposed for Monte Carlo analysis of TRISO fuel particles using the statistical geometry (STG) method. The statistically uniform distribution of fuel particles, which is usually assumed as a default sampling method of flight distance …

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Evaluation of Expansion Reactivity Based on Reactivity Coefficient for Sodium-Cooled Fast Reactor

Satoshi Takeda, Takanori Kitada, Eiji Hoashi, Takafumi Okita

Abstract In this paper, formulas for evaluating expansion reactivity based on reactivity coefficients in sodium-cooled fast reactors are derived, and the approximation errors used in the derivation are also evaluated. This research provides formulas for both Z-axis expansion reactivity and radial expansion …

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Thermal Cut-Off Energy for Accurate Analysis of Prismatic High-Temperature Gas-Cooled Reactor

Satoshi Takeda, Takanori Kitada, Akio Yamamoto, Kazuya Yamaji et autres

Abstract In this study, the appropriate thermal cut-off energy for neutron transport calculations in High-Temperature Gas-cooled Reactor (HTGR) is investigated. The research employs the Monte Carlo calculation code MVP3.0 to evaluate the impact of changing thermal cut-off energy on the multiplication factor …

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