Results 171 to 180 of about 8,017 (212)

The epithermal neutron flux distribution in a nuclear reactor and its effect on epithermal neutron activation analysis

Journal of Radioanalytical Chemistry, 1978
The shape of the epithermal neutron energy distribution has been determined in two irradiation positions of the University of London CONSORT II reactor. The method applied involves cadmium ratio measurements using a series of resonance detectors. Principles of the method and some considerations relative to epithermal neutron activation analysis in ...
T. Bereznai, T. D. Mac Mahon
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A toolkit for epithermal neutron beam characterisation in BNCT

Radiation Protection Dosimetry, 2004
Methods for dosimetry of epithermal neutron beams used in boron neutron capture therapy (BNCT) have been developed and utilised within the Finnish BNCT project as well as within a European project for a code of practise for the dosimetry of BNCT. One outcome has been a travelling toolkit for BNCT dosimetry.
Seren, Tom, Uusi-Simola, Jouni, Kosunen, Antti, Savolainen, Sauli, Auterinen, Iiro   +5 more
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Neutron scattering from α-Ce at epithermal neutron energies

Pramana, 2008
Neutron scattering data, using neutrons of incident energies as high as 2 eV, on α-Ce and α-Ce-like systems such as CeRh2, CeNi2, CeFe2, CeRu2, and many others that point clearly to the substantially localized 4f electronic state in these systems are reviewed. The present interpretation is contrary to the widely held view that the 4f electrons in these
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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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BNCT Epithermal Neutron Beam Mapping by Using Indirect Neutron Radiography

Nuclear Technology, 2009
This paper aims to measure the neutron flux distribution over the cross section of the boron neutron capture therapy epithermal neutron beam at the Tsing Hua Open-pool Reactor (THOR) by using indir...
Yuan-Hao Liu, Chun-Kai Huang, Pi-En Tsai, Ang-Yu Chen, Hong-Ming Liu, Shih-Chung Lee, Shiang-Huei Jiang   +6 more
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Accelerator-based source of epithermal neutrons for neutron capture therapy

Atomic Energy, 2004
Computational studies are performed for choosing an optimal material and dimensions of a moderator for forming a beam of epithermal neutrons for boron-neutron-capture therapy based on a proton accelerator and the reaction 7 Li(p, n)7 Be as the neutron source. It is shown that the best material for this is magnesium fluoride. An optimal configuration is
O. E. Kononov, V. N. Kononov, A. N. Solov’ev, M. V. Bokhovko   +3 more
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Accelerator-Based Epithermal Neutron Beams for Neutron Capture Therapy

1993
Collaborative work on the development of an accelerator-based epithermal neutron beam is underway between the Massachusetts Institute of Technology, Cambridge, MA and Science Research Laboratory, Inc., Somerville, MA. Design of the major hardware components of the accelerator, a 4 mA tandem electrostatic device, commenced one year ago in July 1991 ...
J. C. Yanch, R. E. Shefer, B. J. Hughey, R. E. Klinkowstein   +3 more
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Dose Homogeneity in Boron Neutron Capture Therapy Using an Epithermal Neutron Beam

Radiation Research, 1995
Simulation models based on the neutron and photon Monte Carlo code MCNP were used to study the therapeutic possibilities of the HB11 epithermal neutron beam at the High Flux Reactor in Petten. Irradiations were simulated in two types of phantoms filled with water or tissue-equivalent material for benchmark treatment planning calculations.
M W, Konijnenberg, L G, Dewit, B J, Mijnheer, C P, Raaijmakers, P R, Watkins   +4 more
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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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Self-Powered Neutron Detectors for Measuring Epithermal Neutron Flux

1989
Self-powered neutron detectors (SPNDs) with erbium, hafnium, gadolinium, rhodium, silver, and cobalt emitters have been irradiated in several different neutron and gamma spectra obtained by a variety of filters: cadmium, gadolinium, boron, lead, zirconium, aluminum, or light water.
MN Agu, H Petitcolas
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