Determination of dose effect of thermal neutrons on the basis of external ?-radiation

A. G. Istomina; I. B. Keirim-Markus

doi:10.1007/bf01479791

Determination of the response to photons and thermal neutrons of new LiF based TL materials for radiation protection purposes

IEEE Nuclear Science Symposium Conference Record, 2005 ◽

10.1109/nssmic.2005.1596297 ◽

2006 ◽

Author(s):

R. Bedogni ◽

A. Esposito ◽

M. Angelone ◽

M. Chiti

Keyword(s):

Radiation Protection ◽

Thermal Neutrons

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Experimental determination of the14N(n,p)14Creaction cross section for thermal neutrons

Physical Review C ◽

10.1103/physrevc.61.064601 ◽

2000 ◽

Vol 61 (6) ◽

Cited By ~ 10

Author(s):

J. Wagemans ◽

C. Wagemans ◽

G. Goeminne ◽

P. Geltenbort

Keyword(s):

Experimental Determination ◽

Cross Section ◽

Thermal Neutrons

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Effect of Irradiation Doses on AlCu6.5 Alloy Using Positron Annihilation Doppler Broadening Technique

Defect and Diffusion Forum ◽

10.4028/www.scientific.net/ddf.278.15 ◽

2008 ◽

Vol 278 ◽

pp. 15-24

Author(s):

M. Abdel-Rahman ◽

Yahia A. Lotfy ◽

M.A. Abdel-Rahman ◽

Emad A. Badawi

Keyword(s):

Positron Annihilation ◽

Positron Annihilation Spectroscopy ◽

Dose Effect ◽

Doppler Broadening ◽

Γ Irradiation ◽

Cu Alloy ◽

Versatile Tool ◽

Parameter Values ◽

Line Shape Parameter

Positron Annihilation Spectroscopy (PAS) is a powerful and versatile tool for the study of the microscopic structure of materials. Doppler Broadening Positron Annihilation Technique (DBPAT) is the fastest technique used among positron annihilation techniques. The dose effect in Al-6.5at. % Cu alloy was investigated by means of DBPAT. An abrupt change in both the S and W line-shape parameter values occurred at 70 kGy of irradiation. The S- and W-Parameters of the trapped positrons at 70 kGy of γ−irradiation dose are about 48 % and 14 % respectively. The S- versus W-parameter reveals a linear relationship indicating the presence of only one type of defect. The S- and W-parameters have been used in the determination of the positron trapping rate and the grain size of the AlCu6.5 alloy.

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Dose-effect curves and relative biophasic drug levels: Elucidation of these concepts and the illustration of their use for the determination of bioavailability, rate of absorption, and time course of pharmacological response

Journal of Pharmacokinetics and Biopharmaceutics ◽

10.1007/bf01271445 ◽

1976 ◽

Vol 4 (1) ◽

pp. 67-80 ◽

Cited By ~ 3

Author(s):

William A. Weigand ◽

Ashok K. Jhawar

Keyword(s):

Time Course ◽

Dose Effect ◽

Drug Levels ◽

Pharmacological Response ◽

Rate Of Absorption

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I-129 DETERMINATION IN EVAPORATOR CONCENTRATE USING OXIDATIVE EXTRACTION AND CHROMATOGRAPHIC RESIN

Brazilian Journal of Radiation Sciences ◽

10.15392/bjrs.v9i1a.1248 ◽

2021 ◽

Vol 9 (1A) ◽

Author(s):

Thiago César De Oliveira ◽

Roberto Pellacani Guedes Monteiro ◽

Geraldo Frederico Kastner ◽

Arno Heeren De Oliveira

Keyword(s):

Nuclear Power ◽

Power Plants ◽

Selective Extraction ◽

Thermal Neutrons ◽

X Ray ◽

Tracer Solution ◽

Spectrometry Technique ◽

Chromatographic Resin ◽

Set Up

Determination of long-lived radionuclides is very important for study of the radioactive waste final deposition. In this work will be studied 129I radionuclide which present 1.6 x 107 years half-life, β-particle-emitting (Emax = 194 keV) and X-ray-emitting (E = 29.78 keV). It’s produced primarily from fission of 235U and 239Pu and for fission induced by thermal neutrons. For this reason, radiochemical procedures for 129I determination in evaporator concentrate wastes from nuclear power plants were carried out. The first procedure was based on oxidative extraction and alkaline absorption and the second one, was based on selective extraction using a chromatographic resin in order to separate iodine from its interferents. After the separation steps, the iodine activity was measured by ultra low gamma spectrometry technique. To set up the yield recovery for 129I, a tracer solution of 129I was used in order to follow the behavior of iodine during the separation steps. The yield recovery for iodine was around 75-80% for the first procedure and 80-85% for the second. The two procedures used mutually, ensure a greater efficiency in the separation of iodine from their respective interferents.

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