Re-analysis of the Experimental Leakage Neutron Spectrum from a Silicon Spherical Shell with Incident 14 MeV Neutrons using Different and Modified Neutron Cross Section Libraries

Author(s):  
C Ichihara ◽  
SA Hayashi ◽  
I Kimura ◽  
J Yamamoto ◽  
A Takahashi
2020 ◽  
Vol 239 ◽  
pp. 03017
Author(s):  
Yinghong Zuo ◽  
Jinhui Zhu ◽  
Honggang Xie

To study the effect of temperature dependent neutron cross section on the neutron transmission performance of typical metallic spherical shells, this paper generated the temperature dependent neutron cross section data by using NJOY program, and established the computational model of interaction of neutron with iron and aluminium spherical shell. The temperature evolution of energy spectrum of transmitted neutron and secondary gamma ray, and the number ratio of transmitted neutrons to secondary gamma rays has been studied at various neutron energies. The results show that only when the energies of the incident neutron are in a certain range, the temperature dependent cross sections can have a significant effect on the energy spectrum of the rays penetrating the spherical shell. For different metal materials, the transmitted neutron spectrum and the secondary gamma ray spectrum will be significantly affected when the temperature increases to different high value. Generally, the transmitted neutron number decreases with the increase of temperature, and the number ratio of transmitted neutron to secondary gamma ray also decreases with the increase of temperature, while the changing trend of number of secondary gamma ray with temperature is related to the type of shell material.


Author(s):  
О. О. Грицай ◽  
А. К. Гримало ◽  
В. В. Колотий ◽  
В. М. Венедиктов ◽  
С. П. Волковецький ◽  
...  

1994 ◽  
Vol 31 (3) ◽  
pp. 173-179 ◽  
Author(s):  
Hideo HARADA ◽  
Toshiaki SEKINE ◽  
Yuichi HATSUKAWA ◽  
Noriko SHIGETA ◽  
Katsutoshi KOBAYASHI ◽  
...  

1947 ◽  
Vol 72 (2) ◽  
pp. 109-115 ◽  
Author(s):  
R. B. Sawyer ◽  
E. O. Wollan ◽  
S. Bernstein ◽  
K. C. Peterson

1972 ◽  
Vol 29 (26) ◽  
pp. 1745-1748 ◽  
Author(s):  
P. Stoler ◽  
N. N. Kaushal ◽  
F. Green ◽  
Edward Harms ◽  
Luciano Laroze

Author(s):  
Branislav Vrban ◽  
Stefan Cerba ◽  
Jakub Luley ◽  
Filip Osuský ◽  
Vladimir Necas

Abstract The properties of nuclear fuel depend on the actual isotopic composition which develops during a reactor operation. In practice, the prediction accuracy of burnup calculations serves as the basis for the future precise estimation of a core lifetime and other safety-based core characteristics. The present study quantifies nuclear data induced uncertainties of nuclide concentrations and multiplication factors in VVER-440 fuel depletion analysis. The well-known SCALE system and the TRITON sequence are used with the NEWT deterministic solver in the SAMPLER module that implements stochastic techniques to assess the uncertainty in computed results. The propagation of uncertainties in neutron cross section and fission yields is studied through the depletion calculation of 2D heterogeneous VVER-440 fuel assembly with an average enrichment of 4.87 wt % of 235U and six gadolinium rods with 3.35 % of Gd2O3. In the paper, fixed nominal depletion conditions are based on the real operational data of the Slovak NPP Bohunice unit 4 during cycle 30. In total 250 cases with uncertain parameters are computed and the results are evaluated by an auxiliary tool.


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