scholarly journals RADIATION DAMAGE IN URANIUM TARGET OF THE ACCELERATOR DRIVEN SYSTEM “KIPT NEUTRON SOURCE”

2021 ◽  
pp. 24-28
Author(s):  
V.V. Gann ◽  
A.V. Gann ◽  
B.V. Borts ◽  
I.M. Karnaukhov ◽  
A.A. Parkhomenko

In this work, the rate of radiation damage production in a uranium target of the neutron source at NSC KIPT un-der electrons irradiation with an energy of 100 MeV was estimated. The contribution of elastic and inelastic proc-esses is determined: high-energy electrons and gamma quanta, photo-neutron production, fragments arising from photo-fission, damage from neutrons. It was found that the main input into damage production in a uranium target give fragments of photo-fission.

2021 ◽  
pp. 17-21
Author(s):  
V.V. Gann ◽  
A.V. Gann ◽  
B.V. Borts ◽  
I.M. Karnaukhov ◽  
P.I. Gladkikh ◽  
...  

In this work, mathematical modeling of a complex of processes occurring in a tungsten target under irradiation with high-energy electrons with an energy of 100 MeV: an electromagnetic shower, the production of photo-neutrons, and particle transport along the target, damage from neutrons of the subcritical assembly. It was found that the greatest contribution to the rate of damage formation in a tungsten target give the elastic scattering of high-energy electrons on nuclei.


1971 ◽  
Vol 8 (3) ◽  
pp. 173-175 ◽  
Author(s):  
Itsuro KIMURA ◽  
Shu A. HAYASHI ◽  
Katsuhei KOBAYASHI ◽  
shuji YAMAMOTO ◽  
Toshikazu SHIBATA

1972 ◽  
Vol 11 (2) ◽  
pp. K103-K104 ◽  
Author(s):  
F. Fujimoto ◽  
H. Fujita

2016 ◽  
Vol 2016 ◽  
pp. 1-11 ◽  
Author(s):  
Gizem Bakır ◽  
Gamze Genç ◽  
Hüseyin Yapıcı

This study presents the power flattening and time-dependent neutronic analysis of a conceptual helium gas cooled Accelerator Driven System (ADS) loaded with TRISO (tristructural-isotropic) fuel particles. Target material is lead-bismuth eutectic (LBE). ThO2, UO2, PuO2, and CmO2TRISO particles are used as fuel. PuO2and CmO2fuels are extracted from PWR-MOX spent fuel. Subcritical core is radially divided into 10 equidistant subzones in order to flatten the power produced in the core. Tens of thousands of these TRISO fuel particles are embedded in the carbon matrix fuel pebbles as five different cases. The high-energy Monte Carlo code MCNPX 2.7 with the LA150 library is used for the neutronic calculations. Time-dependent burnup calculations are carried out for thermal fission power (Pth) of 1000 MW using the BURN card. The energy gain of the ADS is in the range of 99.98–148.64 at the beginning of a cycle. Furthermore, the peak-to-average fission power density ratio is obtained between 1.021 and 1.029 at the beginning of the cycle. These ratios show a good quasi-uniform power density for each case. Furthermore, up to 155.1 g233U and 103.6 g239Pu per day can be produced. The considered system has a high neutronic capability in terms of energy multiplication, fissile breeding, and spent fuel transmutation with thorium utilization.


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