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Materials

E-mail address: go_chiba(a)eng.hokudai.ac.jp
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Access to my office (N-317)
  • From main entrance hall of the engineering building
  • From north entrance of the engineering building
Reactor physics fundamentals
  • Overview of reactor physics calculations (2018/12/21)
Programming exercise
  • (1)Solution to quadratic equation
  • (2)Use of array
  • (3)Gaussian elimination (Revised in 2018/12/14)
  • (4)Concept of C++ class (Revised in 2018/3/19)
  • (5)Solving cubic equation by the bisection method and the Newton method
  • (6)Integration of polynomial equation
Reactor physics programming exercise
  • Adjoint equation and perturbation calculation (Revised in 2018/10/30)
  • Neutron multiplication in infinite homogeneous medium with up-scattering (Revised in 2018/12/13) (Cross section data: [UO2][MOX])
General-purpose reactor physics code system CBZ
  • Summary of general-purpose reactor physics code system CBZ (Revised in 2018/5/3)
  • Tutorial (Revised in 2020/2/8)
  • Numerical results of LWR fuel assembly calculations with CBZ/MulticellBurner (Revised in 2020/1/20)
CBZ/FRBurner
  • Users’ manual of CBZ/FRBurner: A module for fast reactor core design (Revised in 2019/8/1)
  • About fuel assembly model in FRBurner (Revised in 2019/11/26)
CBZLIB
  • CBZLIB and advanced Bondarenko model(2020/2/3)
  • Generation procedure of CBZLIB (2020/7/18)
Neutron transport and diffusion equations
  • Derivation of one-dimensional neutron diffusion equation
  • Analytical solution to one-dimensional neutron diffusion eigenvalue equation
Cross section group-collapsing and spatial homogenization
  • Fundamentals of collapsing (or condensation) of multi-group cross section (2019/1/9)
Animation on reactor phyics
  • Numer density changes of heavy metal of LWR fuel during burnup (Unit: GWd/t) UO2:MOX)
  • Radioactivity changes of heavy metal of LWR fuel during burnup and cooling (burnup till step 20)(UO2:MOX)
  • Heat emission changes of heavy metal of LWR fuel during burnup and cooling (burnup till step 20)(UO2:MOX)
  • Neutron flux energy spectra of LWR fuel during burnup (unit: burnup [GWD/t])(UO2:MOX)
  • Adjoint neutron flux energy spectra of LWR fuel during burnup (unit: burnup [GWD/t])(UO2)
  • Number density change of FP nuclides after burst fission of U-235
  • Decay heat change after burst fission of U-235 (Day / Year)
  • Neutron flux change after 10MeV neutron injection to critical fast neutron system (1 ns-order / 100 ns-order)
  • Neutron flux change after 10MeV neutron injection to critical thermal neutron system (1 ns-order / 10 ns-order / 100 ns-order / 1 ms-order)
  • Delayed neutron spectra after 10MeV neutron injection to critical thermal neutron system(The ENDF/B-VII.1 decay data is used.)
  • Angular neutron flux of slab and bare thermal neutron system from core center to peripheral (Fast neutron / Thermal neutron)
  • Angular neutron flux of slab and water-reflected thermal neutron system from core center to peripheral (Boundary: mesh 45) (Fast neutron / Thermal neutron)
  • Neutron flux spactra around 6.67eV resonance of U-238 after scattering source is provided (Background XS: 1 barn)
  • Neutron flux spactra around 6.67eV resonance of U-238 after scattering source is provided (Background XS: 10 barn)
  • Neutron flux spactra around 6.67eV resonance of U-238 after scattering source is provided (Background XS: 100 barn)
Animation of BWR power stability (Ringhals unit 1 cycle 14 LPRM data)
  • Data A (Low power / High flow rate, Decay ratio: global 0.30)
  • Data B (Low power / Middle flow rate)
  • Data C (Low power / Low flow rate, Decay ratio: global 0.69, regional 0.57)
  • Data D (Middle power / Lowh flow rate, Decay ratio: global 0.79, regional 0.75)
  • Data E (Middle power / Middle flow rate, Decay ratio: global 0.67, regional 0.60)
  • Data F (Middle power / High flow rate, Decay ratio: global 0.64, regional 0.59)
  • Data G (High power / Low flow rate, Decay ratio: global 0.80, regional 0.99)
  • Data H (High power / Middle flow rate, Decay ratio: global 0.78, regional 0.79)
  • Data I (High power / High flow rate, Decay ratio: global 0.71, regional 0.63)
MOMENTOF code
  • Manual
Nuclear data
  • Important nuclear data in reactor physics calculations (2018/8/3)
  • Reactor physics parameters and nuclear data relevant to delayed neutrons (2018/8/4)
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