亀山 高範

KAMEYAMA Takanori

  • 教授
  • 学位:博士(工学)

基本情報

所属

  • Undergraduate School of Engineering / Department of Nuclear Engineering
  • Graduate School of Science and Technology / Course of Science and Technology
  • Graduate School of Engineering / Course of Applied Science

詳細情報

研究分野

  • Energy Nuclear engineering nuclear reactor physics, nuclear reactor engineering, nuclear fuel engineering

受賞

  • Atomic energy society of Japan JNST most cited article award Development of Calculation Technique for Iterated Fission Probability and Reactor Kinetic Parameters Using Continuous-Energy Monte Carlo Method

論文

Development of a Compact and Convenient Neutron Diffusion Calculation Code ”S-Dif” for Education and Training

Development of an Educational Monte Carlo Method Code ”S-Monte” for Photon and Neutron Transport Calculation

Verification and Utilization of Tokai University Reactor Simulator (TURS) for Research and Education

Distributions of 242Cm and 244Cm Nuclide Compositions as Neutron Sources and Their Neutron Emission Rates in BWR Spent Fuels based on Three-Dimensional Neutron Transport and Burnup Calculations

Analysis of atomic distribution in as-fabricated Zircaloy-2 claddings by atom probe tomography under high-energy pulsed laser

Observation of c-component dislocation structures formed in pure Zr and Zr-base alloy by self-ion accelerator irradiation (vol 422, pg 167, 2012)

Observation of c-component dislocation structures formed in pure Zr and Zr-base alloy by self-ion accelerator irradiation

Development of Calculation Technique for Iterated Fission Probability and Reactor Kinetic Parameters Using Continuous-Energy Monte Carlo Method

A new passive safety FBR concept of "KAMADO" - Easy replacement from the existing light water reactor to FBR

Core concept of a passive-safety fast reactor "METAL-KAMADO" and reactivity coefficients

Comparison of kinetic parameters based on continuous energy Monte Carlo method and evaluated nuclear data libraries for reactivity of MOX fuel cores

Clarification of rim structure effects on properties and behaviour of LWR UO2 fuels and gadolinia doped fuels

Estimation of 6 groups of effective delayed neutron fraction based on continuous energy Monte Carlo method

Core performance of new concept passive-safety reactor "KAMADO" - Safety, burn-up and uranium resource problem

Proposal of direct calculation of kinetic parameters βeff and based on continuous energy monte carlo method

High Burnup Rim Project: (III) properties of rim-structured fuel

Temperature and fission rate effects on the rim structure formation in a UO2 fuel with a burnup of 7.9% FIMA

Analyses of burnup at plutonium spots in uranium-plutonium mixed oxide fuels in light water reactors by neutron transport and burnup calculations

The FLEXBURN neutron transport code developed by the Sn method with transmission probabilities in arbitrary square meshes for light water reactor fuel assemblies

Dissolution behavior of highly burnt fuel

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