Results 181 to 190 of about 2,664 (222)

Studies on the properties of an epithermal-neutron hydrogen analyzer

Applied Radiation and Isotopes, 2010
Systematic investigations have proved the advantages of the Epithermal Neutron Analyzer (ETNA) for bulk hydrogen analysis as compared to the thermal neutron techniques. Results can contribute, for example, to the design and construction of instruments needed for the detection and identification of plastic anti-personnel landmines, explosives hidden in ...
A, Papp, J, Csikai
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Renovation of epithermal neutron beam for BNCT at THOR

Applied Radiation and Isotopes, 2004
Heading for possible use for clinical trial, THOR (Tsing Hua Open-pool Reactor) at Taiwan was shutdown for renovation of a new epithermal neutron beam in January 2003. In November 2003, concrete cutting was finished for closer distance from core and larger treatment room.
Y-W H, Liu, T T, Huang, S H, Jiang, H M, Liu   +3 more
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Epithermal neutron activation analysis

Journal of Radioanalytical and Nuclear Chemistry Articles, 1985
Different modes of epithermal neutron activation analysis are described. The principles and examples are given for each.
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Enhanced plastic neutron shielding for thermal and epithermal neutrons

Journal of Instrumentation, 2008
We describe a compound made of paraffin and boron carbide (boraffin) deviced to enhance epithermal neutron shielding. The compound is easily prepared and is specially suited to be adapted to particular surfaces. Transmission experiments show a favourable comparison with a commercial rubber-boron carbide compound in the epithermal range.
L A Rodríguez Palomino, J J Blostein, J Dawidowski, G J Cuello   +3 more
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The number of neutrons emitted by Pu239 upon thermal- and epithermal-neutron-induced upon thermal- and epithermal-neutron-induced fission

Journal of Nuclear Energy (1954), 1957
Abstract The mean number v of neutrons emitted during the fission of Pu233 by thermal and epithermal (0·15 to 0·5 eV) neutrons has been measured, and found to be the same within 2% for both cases.
V.I. Kalashnikov, V.I. Lebedev, L.A. Mikaelyan, M.I. Pevzner   +3 more
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Fast- and epithermal-neutron flux measurement

Nuclear Instruments and Methods, 1974
Abstract The feasibility of applying fission-produced 140 Ba to determine fast- and epithermal-neutron fluxes was investigated experimentally. 140 Ba decays by beta-ray emission with a half-life of 12.8 d 1 to 140 La. The absolute activity of 140 La calculated from the measured activity of the 1596.2 keV peak with a calibrated Ge(Li) detector ...
N. Lavi, Z. Fishelzon
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Epithermal Neutron Capture in Uranium-238

Nuclear Science and Engineering, 1977
Designers of thermal-neutron reactors have always had to adjust microscopic nuclear cross sections to predict neutron multiplication in slightly enriched uranium lattices.
H. I. Liou, R. E. Chrien
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Activation analysis of human diet samples with epithermal neutrons

Biological Trace Element Research, 1990
Activation of diet samples by epithermal reactor neutrons is a very sensitive method for the determination of iodine. The method was developed and optimized for its determination. However, it turned out that with the same measurement valid results were also obtained for Br, Cl, K, Na, and P.
Tobler L, Furrer V, Wyttenbach A
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Contribution of epithermal activation in neutron in vivo activation

Physics in Medicine & Biology, 1976
It is pointed out that epithermal activation is not negligible in the in vivo neutron activation analysis (IVNAA) technique for the measurement of skeletal Ca. Multi-group calculations have been carried out to determine the ratio of epithermal to thermal flux and the epithermal activation was measured using the Cd subtraction technique.
Y S, Horowitz, A, Dubi, S, Mordechai
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Design of a californium-based epithermal neutron beam for neutron capture therapy

Physics in Medicine and Biology, 1993
The potential of the spontaneously fissioning isotope, 252Cf, to provide epithermal neutrons for use in boron neutron capture therapy (BNCT) has been investigated using Monte Carlo simulation. The Monte Carlo code MCNP was used to design an assembly composed of a 26 cm long, 11 cm radius cylindrical D2O moderator followed by a 64 cm long Al filter ...
J C, Yanch, J K, Kim, M J, Wilson
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