A Bent Crystal Neutron Spectrometer and Its Application to Neutron Cross-Section Measurements

1947 ◽  
Vol 72 (2) ◽  
pp. 109-115 ◽  
Author(s):  
R. B. Sawyer ◽  
E. O. Wollan ◽  
S. Bernstein ◽  
K. C. Peterson
Keyword(s):  
Cross Section ◽  
Neutron Cross Section ◽  
Neutron Spectrometer ◽  
Bent Crystal

Investigation of the total neutron cross section for natural hafnium on the filtred neutron beam with energy 59 keV

2011 ◽  
Vol 30 (0) ◽  
pp. 142-147
Author(s):  
О. О. Грицай ◽  
А. К. Гримало ◽  
В. В. Колотий ◽  
В. М. Венедиктов ◽  
С. П. Волковецький ◽  
...  
Keyword(s):  
Cross Section ◽  
Neutron Beam ◽  
Neutron Cross Section ◽  
Total Neutron ◽  
Total Neutron Cross Section

Measurement of the Thermal Neutron Cross Section of the90Sr(n, γ)91Sr Reaction

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

Total Neutron Cross Section of Deuterium below 1000 keV

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

Cross Section and Fission Yields Induced Uncertainty in the Vver-440 Burnup Calculation

2021 ◽  
Author(s):  
Branislav Vrban ◽  
Stefan Cerba ◽  
Jakub Luley ◽  
Filip Osuský ◽  
Vladimir Necas
Keyword(s):  
Cross Section ◽  
Neutron Cross Section ◽  
Nuclear Data ◽  
Reactor Operation ◽  
Precise Estimation ◽  
Stochastic Techniques ◽  
Core Characteristics ◽  
Fission Yields ◽  
Operational Data ◽  
Burnup Calculation

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.

Total Neutron Cross Section forC12from 500 kev to 1350 kev

1960 ◽  
Vol 117 (4) ◽  
pp. 1055-1056 ◽  
Author(s):  
C. M. Huddleston ◽  
R. O. Lane ◽  
L. L. Lee ◽  
F. P. Mooring
Keyword(s):  
Cross Section ◽  
Neutron Cross Section ◽  
Total Neutron ◽  
Total Neutron Cross Section
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