scholarly journals Vertical and horizontal variations of the fast neutron flux in a single irradiation capsule and their significance in the laser-heating 40Ar/39Ar analysis: Case study for the hydraulic rabbit facility of the JMTR reactor, Japan.

1998 ◽  
Vol 32 (4) ◽  
pp. 243-252 ◽  
Author(s):  
Osamu Ishizuka
Keyword(s):  
Neutron Flux ◽  
Fast Neutron ◽  
Laser Heating ◽  
Fast Neutron Flux ◽  
Horizontal Variations

scholarly journals Глубокие центры радиационных дефектов в монокристаллах CdZnTe, созданные потоком быстрых нейтронов

2018 ◽  
Vol 52 (3) ◽  
pp. 322 ◽  
Author(s):  
С.В. Пляцко ◽  
Л.В. Рашковецкий
Keyword(s):  
Activation Energy ◽  
Neutron Flux ◽  
Fast Neutron ◽  
Single Crystals ◽  
Isothermal Annealing ◽  
Fast Neutron Flux ◽  
Photoluminescence Properties ◽  
Radiation Induced ◽  
Induced Defects

AbstractThe effect of a fast neutron flux (Φ = 10^14–10^15 cm^–2) on the electrical and photoluminescence properties of p -CdZnTe single crystals is studied. Isothermal annealing is performed ( T = 400–500 K), and the activation energy of the dissociation of radiation-induced defects is determined at E _D ≈ 0.75 eV.

Fast Neutron Irradiation Optimization of Thorium-Fueled SCWR Reactor Pressure Vessel

2020 ◽  
Vol 6 (3) ◽  
Author(s):  
Petra Pónya ◽  
Gyula Csom ◽  
Sándor Fehér
Keyword(s):  
Neutron Flux ◽  
Fast Neutron ◽  
Neutron Irradiation ◽  
Pressure Vessel ◽  
Flow Direction ◽  
Reactor Pressure Vessel ◽  
Fast Neutron Flux ◽  
Inner Surface ◽  
Fast Neutron Irradiation ◽  
Reactor Pressure

Abstract Fast neutron irradiation causes embrittlement of the reactor pressure vessel (RPV) material; therefore, it may end operation life before design lifetime. Well-known method to recuperate crystal lattice dislocations is annealing. In the current version of thorium fueled supercritical water-cooled reactor (SCWR) design proposed by the Institute of Nuclear Technology at Budapest University of Technology and Economics (BME NTI), the supercritical fluid flows upward between the core barrel and the inner surface of the RPV thereby, the coolant would keep the RPV's temperature at ∼500 °C. This reverse coolant flow direction would decrease the embrittlement of RPV by constant annealing. To minimize the fast neutron flux increase, a relatively thin shielding connected to the inner surface of the barrel could be used. This presents fast neutron irradiation analysis, performed for different settings of the shielding to reduce fast neutron flux reaching the inner surface of RPV.

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