Neutron Cross Sections, Volume 2, Neutron Cross Section Curves

1989 ◽  
Vol 281 (1) ◽  
pp. 250
Author(s):  
Gösta Rudstam
Keyword(s):  
Cross Section ◽  
Cross Sections ◽  
Neutron Cross Section ◽  
Neutron Cross Sections

The Thermal Neutron Cross Section and the Resonance Integral of 184Os, 190Os, 192Os, 64Zn, 68Zn and 59Co

1968 ◽  
Vol 9 (2-3) ◽  
Author(s):  
J. I. Kim ◽  
F. Adams
Keyword(s):  
Neutron Activation ◽  
Thermal Neutron ◽  
Cross Section ◽  
Cross Sections ◽  
Neutron Cross Section ◽  
Resonance Integral ◽  
Activation Measurement ◽  
Thermal Neutron Cross Section ◽  
Neutron Cross Sections

SummaryBy neutron activation measurement with a cadmium filter, using gold as a standard monitor, the thermal neutron cross sections and the resonance integrals of

The total neutron cross-sections of cobalt, silver, iodine, aluminium, nickel and gallium between 1 eV and 5 keV

1952 ◽  
Vol 215 (1121) ◽  
pp. 278-289 ◽  
Keyword(s):  
Total Cross Section ◽  
Cross Section ◽  
Cross Sections ◽  
Neutron Cross Section ◽  
Total Neutron ◽  
Total Neutron Cross Section ◽  
Energy Research ◽  
Main Interest ◽  
Neutron Time ◽  
Neutron Cross Sections

This paper presents experimental results of total neutron cross-section measurements made with a neutron time of flight spectrometer at the Atomic Energy Research Establishment, Harwell. Six elements, Co, Ag, I, Al, Ni and Ga, have so far been studied over the range of neutron energies from 1 eV to 5 keV. The main interest of the measurements lies in the use of improved resolution at the higher energies with the result that certain levels have now been more clearly resolved. The results are presented as curves showing the variation of total cross-section with neutron energy. For certain levels, the strength of the resonance is calculated. The spectrometer is briefly described and some reference made to previous work in the same field.

A new empirical formula for cross-sections of (n,nα) reactions

2020 ◽  
Vol 29 (08) ◽  
pp. 2050062
Author(s):  
Mustafa Yiğit
Keyword(s):  
Cross Section ◽  
Cross Sections ◽  
Empirical Formula ◽  
Nuclear Reactions ◽  
Measured Cross Section ◽  
Future Studies ◽  
Present Formalism ◽  
The Cross ◽  
Neutron Cross Sections ◽  
Good Agreement

Studies on the cross-sections of (n,n[Formula: see text]) reactions which are energetically possible, about 14 MeV neutrons are quite scarce. In this paper, the cross-sections of (n,n[Formula: see text] nuclear reactions at [Formula: see text]14–15 MeV are analyzed by using a new empirical formula based on the statistical theory. We show that neutron cross-sections are closely related to the [Formula: see text]-value of nuclear reaction, in particular for (n,n[Formula: see text]) channels. Results obtained with this empirical formula show good agreement with the available measured cross-section values. We hope that the estimations on the cross-sections using the present formalism may be helpful in future studies in this field.

scholarly journals nxs: a program library for neutron cross section calculations

2012 ◽  
Vol 45 (3) ◽  
pp. 603-607 ◽  
Author(s):  
Mirko Boin
Keyword(s):  
Crystal Structure ◽  
Instrument Development ◽  
Cross Section ◽  
Graphical User Interface ◽  
Cross Sections ◽  
Neutron Cross Section ◽  
Absorption Cross ◽  
Program Library ◽  
Imaging Experiment ◽  
Experiment Validation

A collection of routines for calculating neutron scattering and absorption cross sections on the basis of crystal structure descriptions is presented and implemented in the new and reusablenxsprogram library. An example program providing a graphical user interface to thenxsfunctions is created to demonstrate their usage. The flexibility of the library and the possibilities for multiple areas of application are shown by further examples involving Monte Carlo neutron simulations concerned with imaging experiment validation and neutron instrument development.

scholarly journals Investigation of fast neutron shielding properties of new polyurethane-based composites loaded with B4C, BeO, WO3, ZnO, and Gd2O3 micro-and nanoparticles

2019 ◽  
Vol 25 (4) ◽  
pp. 211-219 ◽  
Author(s):  
Asghar Mesbahi ◽  
Khatibeh Verdipoor ◽  
Farhad Zolfagharpour ◽  
Abdolali Alemi
Keyword(s):  
Cross Section ◽  
Cross Sections ◽  
Neutron Cross Section ◽  
Radiation Shielding ◽  
Fast Neutrons ◽  
Nano Composites ◽  
Monte Carlo Code ◽  
Neutron Shielding ◽  
Shielding Properties ◽  
Polyurethane Matrix

Abstract The aim of the current research was to study the radiation shielding properties of polyurethane-based shielding materials filled with B4C, BeO, WO3, ZnO, and Gd2O3 particles against fast neutrons. The macroscopic cross sections of composites containing micro- and nanoparticles with a diameter of 10 µm and 50 nm were calculated using MCNPX (2.6.0) Monte Carlo code. The results showed that adding nano-scaled fillers to polyurethane matrix increases attenuation properties of neutron shields compared to micro-scaled fillers for intermediate and fast neutrons. Among the studied composites, WO3 and Gd2O3 nano-composites presented higher neutron cross section compared to others.

THE NEUTRON CAPTURE CROSS SECTIONS OF Pu238, Pu242, AND Am243 IN THE THERMAL AND EPICADMIUM REGIONS

1957 ◽  
Vol 35 (2) ◽  
pp. 147-154 ◽  
Author(s):  
J. P. Butler ◽  
M. Lounsbury ◽  
J. S. Merritt
Keyword(s):  
Thermal Neutron ◽  
Cross Section ◽  
Cross Sections ◽  
Neutron Capture ◽  
Neutron Cross Section ◽  
Fission Cross Section ◽  
Capture Cross ◽  
Mass Analysis ◽  
Thermal Neutron Cross Section ◽  
Capture Cross Sections

Thermal neutron capture cross sections of 403 ± 8 b. for Pu238, 18.6 ± 0.8 b. for Pu242, and 73.6 ± 1.8 b. for Am243 have been measured by the activation method assuming 36.4 b. for the thermal neutron cross section of Co59. Samples of plutonium (90% Pu242 – 10% Pu238) were irradiated for 1 to 5 months in the NRX reactor. The growth of Pu239, Am243 (the daughter of the 5 hr. Pu243), and Cm244 (the daughter of the 25 min. Am244) was determined by mass analysis and by alpha spectrum analysis and total alpha counting. Resonance capture integrals (from 0.5 ev. to ∞) of 3260 ± 280 b. for Pu238, 1275 ± 30 b. for Pu242, and 2290 ± 50 b. for Am243 were found using cobalt and U238 as standards. Values of 48.6 b. and 282 b. were taken as the resonance integrals of Co59 and U238 respectively.The fission cross section of Pu242 was zero within experimental error.

Excitation Curves for the Reactions of Fast Neutrons with Zinc

1972 ◽  
Vol 50 (20) ◽  
pp. 2536-2548 ◽  
Author(s):  
D. C. Santry ◽  
J. P. Butler
Keyword(s):  
Neutron Flux ◽  
Cross Section ◽  
Cross Sections ◽  
Fission Neutron ◽  
Fast Neutrons ◽  
Factors Influencing ◽  
Fission Neutron Spectrum ◽  
Neutron Cross Sections ◽  
Threshold Energies ◽  
Measure Cross Section

The activation method was used to measure cross section values from threshold energies up to 20 MeV for the reactions 64Zn(n,p)64Cu, 68Zn(n,α)65Ni, and 70Zn(n,2n)69Znm. The neutron flux at energies below 5.3 MeV was determined with a calibrated neutron long counter while at higher energies measurements were made relative to the known cross section for the 32S(n,p)32P reaction. Effective cross sections for a fission-neutron spectrum calculated from measured excitation curves are 42.3 ± 2.1 mb for the (n,p) reaction, 0.035 ± 0.003 mb for the (n,α) reaction, and 0.45 ± 0.04 mb for the (n,2n) reaction. Factors influencing precise measurements of fast-neutron cross sections are discussed in detail.

scholarly journals Total neutron cross-section extracted from transmission experiments with liquid oxygen using neutron energies from 18 to 27 MeV

2020 ◽  
Vol 239 ◽  
pp. 20008
Author(s):  
Martin Ansorge ◽  
Pavel Bém ◽  
David Hladík ◽  
Mitja Majerle ◽  
Jaromír Mrázek ◽  
...  
Keyword(s):  
Cross Section ◽  
Cross Sections ◽  
Nuclear Physics ◽  
Neutron Cross Section ◽  
Liquid Oxygen ◽  
Total Neutron Cross Section ◽  
Physics Institute ◽  
Target Station ◽  
Transmission Measurements ◽  
Nuclear Physics Institute

Fast neutron generators driven by isochronous cyclotron U-120M developed at Nuclear Physics Institute were used for neutron cross-section measurements. The target station with 2 mm thin lithium was used to produce pulsed beams of fast quasi-monoenergetic neutrons in the 7Li(p,n) reaction. The Time-of-Flight technique was used to determine the exact neutron energy spectra. The transmission measurements on liquid oxygen were conducted for several neutron peak energies between 18 and 27 MeV and the cross-sections for reaction natO(n,tot) were derived.

scholarly journals Setup for the measurement of the 235U(n, f) cross section relative to n-p scattering up to 1 GeV

2020 ◽  
Vol 239 ◽  
pp. 01008
Author(s):  
A. Manna ◽  
O. Aberle ◽  
V Alcayne ◽  
S. Amaducci ◽  
J. Andrzejewski ◽  
...  
Keyword(s):  
Cross Section ◽  
Cross Sections ◽  
Recoil Proton ◽  
High Energy ◽  
Section Data ◽  
Nuclear Systems ◽  
Biological Effectiveness ◽  
Induced Fission ◽  
Set Up ◽  
Neutron Cross Sections

The neutron induced fission of 235U is extensively used as a reference for neutron fluence measurements in various applications, ranging from the investigation of the biological effectiveness of high energy neutrons, to the measurement of high energy neutron cross sections of relevance for accelerator driven nuclear systems. Despite its widespread use, no data exist on neutron induced fission of 235U above 200 MeV. The neutron facility n_TOF offers the possibility to improve the situation. The measurement of 235U(n,f) relative to the differential n-p scattering cross-section, was carried out in September 2018 with the aim of providing accurate and precise cross section data in the energy range from 10 MeV up to 1 GeV. In such measurements, Recoil Proton Telescopes (RPTs) are used to measure the neutron flux while the fission events are detected and counted with dedicated detectors. In this paper the measurement campaign and the experimental set-up are illustrated.

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