Download or read book Neutron Spectrum Calculations for a Fast neutron Generator Having an Annular Ion Source written by Beni M. Bahal and published by . This book was released on 1983 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Handbook of Fast Neutron Generators Volume I written by Julius Csikai and published by CRC Press. This book was released on 1987-09-30 with total page 264 pages. Available in PDF, EPUB and Kindle. Book excerpt: This handbook reviews those problems and methods of science and technology where the neutrons produced in the 3H/d, N/4He, and 2H/d, n/3He reactions play the main role. This two-volume set: Discusses possible applications of these small generators as thermal neutron sources Enables suitable topics to be selected for education and training, provides a wide range of experiments with the detection of neutrons and charged particles, including the study of shielding and the generator technology itself Gives a review of important operational characteristics of neutron generators and the necessary instruments connected with these applications Provides an account of recent results of fast neutron activation analysis in various fields.

Download or read book Handbook of Fast Neutron Generators Volume II written by Julius Csikai and published by CRC Press. This book was released on 1987-09-30 with total page 248 pages. Available in PDF, EPUB and Kindle. Book excerpt: This handbook reviews those problems and methods of science and technology where the neutrons produced in the 3H/d, N/4He, and 2H/d, n/3He reactions play the main role. This two-volume set: Discusses possible applications of these small generators as thermal neutron sources Enables suitable topics to be selected for education and training, provides a wide range of experiments with the detection of neutrons and charged particles, including the study of shielding and the generator technology itself Gives a review of important operational characteristics of neutron generators and the necessary instruments connected with these applications Provides an account of recent results of fast neutron activation analysis in various fields.

Download or read book Fast neutron Spectrum of the LITR written by Robert G. Cochran and published by . This book was released on 1955 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book INIS Atomindeks written by and published by . This book was released on 1985 with total page 1566 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book MUFT 4 written by Henry Bohl and published by . This book was released on 1957 with total page 72 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book MUFT Revision written by Robert A. Grimesey and published by . This book was released on 1962 with total page 60 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Physics Briefs written by and published by . This book was released on 1990 with total page 1286 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Construction and Calibration of a Fast Neutron Spectrum Generator written by Kenneth Dwight Dobbin and published by . This book was released on 1974 with total page 228 pages. Available in PDF, EPUB and Kindle. Book excerpt: A standard fast reactor spectrum can be created by the partial moderation of the U-235 fission spectrum in an air cavity. Spherical natural uranium shells are driven by thermal neutrons from a thermal column. The uranium is placed at the center of a spherical graphite hohlraum to reduce the anisotropic effect of a planar source of thermal neutrons. The Oregon State University (OSU) fast neutron spectrum facility design employs this method which is being used by Albert Fabry in Mol, Belgium and the NISUS assembly in London, United Kingdom, to create a fast neutron spectrum. The OSU facility uses the ther malizing column of a TRIGA Mark II reactor for a thermal neutron source. The mechanical design is presented showing the location of the facility, the aluminum container and internals, and the transport assembly. Two computer codes are introduced in the nuclear design. SLAB is a first approximation diffusion theory code which justifies the use of one foot of graphite backed with water in place of "infinite graphite." FASTSPEC is a diffusion theory approximation code in spherical geometry which shows that the design will produce a spectrum characteristic of a fast reactor. Phase I operation is a mechanical test, health physics evaluation, and a thermal neutron calibration of the facility with a thermal neutron absorber in place of the uranium. The data for phase I is included. Phase II operation will be the insertion of an uranium driver shell and the calibration of the fast spectrum. Only phase I is complete at this time.

Download or read book A Method for Intercalibrating of Neutron Sources with Different Spectra written by A. Wattenberg and published by . This book was released on 1950 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Neutron Sources written by Henry Herman Barschall and published by Pergamon. This book was released on 1983 with total page 378 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Tailoring the Neutron Spectrum from a 14 MeV Neutron Generator to Approximate a Spontaneous Fission Spectrum written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Many applications of neutrons for non-invasive measurements began with isotopic sources such as AmBe or Cf-252. Political factors have rendered AmBe undesirable in the United States and other countries, and the supply of Cf-252 is limited and significantly increasing in price every few years. Compact and low-power deuterium-tritium (DT) electronic neutron generators can often provide sufficient flux, but the 14-MeV neutron spectrum is much more energetic (harder) than an isotopic neutron source. A series of MCNP simulations were run to examine the extent to which the 14-MeV DT neutron spectrum could be softened through the use of high-Z and low-Z materials. Some potential concepts of operation require a portable neutron generator system, so the additional weight of extra materials is also a trade-off parameter. Using a reference distance of 30 cm from the source, the average neutron energy can be lowered to be less than that of either AmBe or Cf-252, while obtaining an increase in flux at the reference distance compared to a bare neutron generator. This paper discusses the types and amounts of materials used, the resulting neutron spectra, neutron flux levels, and associated photon production.

Download or read book SPIC 1 written by P. Gillis and published by . This book was released on 1959 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Calculation of Fast Neutron Spectra from Foil Data written by Gerald Alex Pliner and published by . This book was released on 1969 with total page 338 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book A Standard Neutron Spectrum Source of Application to Fast Reactor Physics written by John Carter Alfred Emmett and published by . This book was released on 2000 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Calculation of Angular Neutron Spectra from the Thick Target Li p n Source written by M. T. Rainbow and published by . This book was released on 1977 with total page 21 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Measurement of Fast Neutron Spectra in an Infinite Medium of written by A. E. Profio and published by . This book was released on 1965 with total page 144 pages. Available in PDF, EPUB and Kindle. Book excerpt: Measurements of the fast neutron spectrum and angular distribution in a large assembly of paraffin wax (CH2) were performed. Two targets were irradiated with a pulsed electron beam from a linear accelerator, one an essentially point isotropic fission spectrum source and the other a narrow photoneutron source for small angle measurements. The time-of-flight technique was employed to measure the energy from approximately 0.3 Mev to approximately 15 Mev with an energy resolution of 10 percent. Estimated error in the spectrum is =10 percent from 0.5 to 8 Mev and =20 percent outside this range. The source spectra were measured in air for input to calculations. Data were obtained at 0 deg up to 15 cm penetration with preliminary results to 45 cm. Angular flux measurements were made up to 60 deg at 30 cm, with preliminary data at 8 deg and 45 cm. The results, within the stated accuracy and resolution, should be suitable for testing analytical techniques and corresponding shielding codes. (Author).