The neutron capture cross-section of 10B decreases smoothly with increasing neutron energy, so that slow-moving (thermal) neutrons are the most likely to be 

1959), thus confirming the 1/v behavior of this cross section up to 100 keV neutron energy, in full agreement with the direct-capture calculation. The fairly 

The thermal neutron capture cross sections (GO) and the resonance integrals (Io) of some fission products (FP), such as 137Cs, ^Sr, wTc, 129I and 135Cs, were measured by the activation and y-ray spectroscopic methods. Moreover, the cross section measurements were done for other FP elements, such as I27I, 133Cs arid I34Cs. This paper provides

Radiative capture and fission are much more likely for slow neutrons than for fast TABLE I. Thermal Neutron Cross Sections of Fuel Atoms (in Barns).

This report describes neutron capture cross sections in the range 10~5 eV - 20 MeV Table 3: The number of capture reactions from each data source in the 

Download Table | Derived neutron capture cross sections of 77 Se from publication: Measurements of keV-Neutron Capture Cross Sections and Capture Gamma-Ray Spectra of

OSTI.GOV Journal Article: Neutron capture cross section of niobium-93 from 2.6 to 700 keV. Neutron capture cross section of niobium-93 from 2.6 to 700 keV. Full Record; Other Related Research;

Neutron capture and fission reaction cross sections are usually measured cross section following in Table 2 should be reduced by 0.05 barn to obtain the.

Neutron capture and total cross sections of 155Gd and 157Gd were measured with the neutron time-of-flight method in Accurate Neutron-Nucleus Reaction measurement Instrument at Material and Life Science Experimental Facility of the Japan Proton Accelerator Research Complex using the NaI (Tl) spectrometer and Li-glass detectors.

The neutron capture cross sections of the two gallium isotopes not chart of nuclei) since neutron capture time scales.

The evaluated capture resonance integrals of the isotopes and natural elements are summarized in the last column of Tables. I and II, in which an asterisk 

Average radiative capture cross sections for 7- to 170 kev neutrons, Table 1. Total cross section for aluminium as a function of energy, cf. p. 3-4.

Table 1 . In the past, many experimental groups have measured the neutron capture cross sections of 153Eu using the time-of-flight (TOF) method.

The neutron cross section σ can be defined as the area in cm2 for which the number of neutron-nuclei reactions taking place is equal to the product of the 

series of measurements of neutron-capture cross sections have been performed on medium-mass ters of the different activation runs are given in Table 1.

From Wikipedia the free encyclopedia Nuclear physics; Nucleus · Nucleons (p, n) · Nuclear matter · Nuclear force · Nuclear structure · Nuclear reaction

The Atlas of Neutron Capture Cross Sections (NGATLAS) contains cross sections data of neutron induced reactions for targets up to, and including, curium (Z=96). It comprises 739 target isotopes with half-lives above 0.5 day. Cross sections to ground, first and second isomers are listed separately.

Among the significant findings are the following. The neutron width of the largest resonance in Gd, at 0.032 eV in 157Gd, has been measured to be (9 6 1)% smaller than that given in ENDF/B-VI updated through release 8. The thermal (2200 m/s) capture cross section of157Gd has been measured to be 11%

All of this data was taken from the Special Feature section of neutron scattering lengths and cross sections of the elements and their isotopes in Neutron News, Vol. 3, No. 3, 1992, pp. 29-37. The scattering lengths and cross sections only go through element number 96 Cm (Curium) A long table with the complete list of elements and isotopes is

966.6-3. 1.432. 966.7-3. 887.5-3. 1.432. 1.385 = 1.404. 710.0-3. *. Page 6. NUCLIDE REACTION FILE. 3-LI- 6 INELAST. (N, 2N+A). CAPTURE. (N,P). ( 

The necessary information on the neutron capture cross sections and -decay the nuclide chart where very few MACS values are available for -capture cross 

Au197(n,γ) cross section in the resonance region

The neutron capture cross sections of 1 7 5 Lu and 1 7 6 Lu have been measured in the energy range from 3 to 225 keV at the Karlsruhe 3.7 MV Van de Graaff accelerator. Neutrons were produced via the 7 Li(p, n) 7 Be reaction by bombarding metallic Li targets with a pulsed proton beam and capture events were registered with the Karlsruhe 4π

The neutron capture cross sections of {sup 114}Sn, {sup 115}Sn, {sup 116}Sn, {sup 117}Sn, {sup 118}Sn, and {sup 120}Sn were measured in the energy range from 3 to 225 keV at the Karlsruhe 3.75 MV Van de Graaff accelerator. Neutrons were produced via the {sup 7}Li({ital p},{ital n}){sup 7}Be reaction using a pulsed proton beam.

Neutron capture and total cross sections of 155Gd and 157Gd were measured with the neutron time-of-flight method in Accurate Neutron-Nucleus Reaction measurement Instrument at Material and Life Science Experimental Facility of the Japan Proton Accelerator Research Complex using the NaI (Tl) spectrometer and Li-glass detectors.

The advantage of using heavy water for neutron moderation is that its low thermal neutron capture cross section ( (th), Table 19.3) improves the neutron economy (i.e. 1 - p becomes much less than in LWRs) so that even natural uranium can be used as fuel.

The cross section is not in general equal to the actual area of the nucleus. For instance the radiative capture cross section for Au197 at the peak of 4.9 eV resonance is 3x10-20 2cm , whereas the geometrical area of its nucleus is just 1.938x10-24 cm2. The reaction cross section is much greater than the physical cross section of the nucleus

In the astrophysically relevant energy range, 9Be belongs to the handful of isotopes among the entire periodic table. (together with carbon, nitrogen, oxygen, 

103 rows · This Neutron Cross Section table gives the Neutron Cross Section of all the elements

The results are summarized in Table 1. The trailing digits in parentheses give the standard errors calculated from the S.F. Mughabghab, Neutron Cross Sections, Vol. 1, Part B: Z = 61 - 100 (Academic Press, New York, 1984). 11. H.D. Young, Statistical Treatment of Experimental Data (McGraw-Hill, New York, 1962).

1 he thermal neutron capture cross sections of NaZ3 and Mn55 have been de- termined using the activation method. The values are 0.53 f. 0.03 and 12.7.