The resonance neutron capture cross section of /sup 89/Y has been measured between 2.5 and 100 keV with the neutron capture facility at the 40-m flight station on the Oak Ridge Electron Linear Accelerator. Resonance parameters were extracted for levels below 50-keV bombarding energy.
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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
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The necessary information on the neutron capture cross sections and -decay the nuclide chart where very few MACS values are available for -capture cross
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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
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If neutron absorption leads to radioactivity, column four lists its half-life. Usually, this activity is caused by radiative capture of neutrons; in those few
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DOI: 10.1103/PHYSREVC.54.1451 Corpus ID: 44322953; Stellar neutron capture cross sections of the tin isotopes. @article{Wisshak1996StellarNC, title={Stellar neutron capture cross sections of the tin isotopes.}, author={Wisshak and Voss and Theis and K{\"a}ppeler and Guber and Kazakov and Kornilov and Reffo}, journal={Physical review.
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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.
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Currently, the ratio of the dose for fast neutrons over epithermal neutron fluence is accepted to be from 2.5·10 -13 to 13·10 -13 Gy·cm 2 /n and from 1·10 -13 to 13·10 -13 Gy·cm 2 /n in case
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Abstract. lead isotopes were obtained at the Oak Ridge electron linear accelerator, in th e neutron energy range above 2.5 keV. These were analyzed for cluded in a new evaluation of lead cross
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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.
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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.
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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.
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Currently, the ratio of the dose for fast neutrons over epithermal neutron fluence is accepted to be from 2.5·10 -13 to 13·10 -13 Gy·cm 2 /n and from 1·10 -13 to 13·10 -13 Gy·cm 2 /n in case
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Table of Contents 1 Introduction 2 Nuclear Data Evaluation 3 Results 4 Summary. Introduction Overview Capture cross section FIESTA , Eldorado Hotel, Santa Fe, NM H. I. Kim 23. Results Cross Section Neutron Cross Section Evaluation of U-238 Author:
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Xenon-135 is a product of U-235 fission and has a very large neutron capture cross-section (about 2.6 x 106 barns). Boronis commonly used as a neutron absorber due to the high neutron cross-section of isotope 10B. Its (n,alpha) reaction cross-section for thermal neutrons is about 3840 barns (for 0.025 eV neutron).
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an experimental (n,γ) cross section is reported for the first time. The results are compared with the ENDF, EAF, and TENDL evaluations. Maxwellian-averaged cross sections were also calculated using the same input γSF and LD functions. DOI: 10.1103/PhysRevC.101.014619 I. INTRODUCTION Neutron-capture reactions play a critical role in a variety
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Keywords: Neutron radiative capture process, primordial nucleosynthesis, nuclear astrophysics, cross sections, cluster model. 1. Introduction Although, the radiative neutron capture reactions on 14C and 14N at astrophysical energies do not take part in the main thermonuclear cycles [1–3] directly, they can
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The 6 Li and 10 B nuclei, for thermal neutrons, have a very high value of (n, ) cross-section and a very small capture cross-section (Mughabghab, 2003), (Brusegan, 2004). The present computer
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5 Neutron reaction cross sections •Total microscopic neutron cross section is expressed as: σ= dN/dt / [(I/A) n A ∆x] • Defining neutron flux as: φ= I/A (neutrons/sec.cm2) • Then: dN/dt = φ(A ∆x n σ) • Neutron flux can also be defined: φ= nnvn where: nn is neutron density per cm3 in beam, vn relative velocity (cm/sec.) of neutrons in beam
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scenario, lead to its release in the environment during long-term storage. But, after neutron capture, 99Tc becomes 100Tc, decaying to the stable isotope 100Ru with a half-life of 16 s. Therefore, 99Tc is a very good candidate for transmutation. Several measurements of the neutron cross sections of 99Tc have been performed in the past [1-5]
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In the astrophysically relevant energy range, 9Be belongs to the handful of isotopes among the entire periodic table. (together with carbon, nitrogen, oxygen,
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