Materials – 原子炉工学研究室

From main entrance hall of the engineering building
From north entrance of the engineering building

Overview of reactor physics calculations (2018/12/21)

(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

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])

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)

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 and advanced Bondarenko model（2020/2/3）
Generation procedure of CBZLIB (2020/7/18)

Derivation of one-dimensional neutron diffusion equation
Analytical solution to one-dimensional neutron diffusion eigenvalue equation

Fundamentals of collapsing (or condensation) of multi-group cross section (2019/1/9)

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）

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)

Manual

Important nuclear data in reactor physics calculations (2018/8/3)
Reactor physics parameters and nuclear data relevant to delayed neutrons (2018/8/4)