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Showing 1 to 10 of 10 for “"thermal neutron flux"”.

  1. The Determination of the Thermal Neutron Flux in a Research Reactor

    Since a research reactor serves as a neutron source for a large number of experiments, knowledge of the neutron flux, and of its spatial and spectral energy distribution is of great importance, not only for purposes of experimental reactor physics (e.g., determination of specific data with regard …

    creighton Repository record for The Determination of the Thermal Neutron Flux in a Research Reactor (opens in a new tab)

  2. An application of Chebyshev polynomials to the solution of a two-dimensional elliptic boundary-value problem

    … to approximate solutions to the two-dimensional neutron diffusion equation. The two-dimensional two-group neutron diffusion equations are solved by expanding neutron fluxes in a finite series of Chebyshev polynomials over large regions of a fission reactor. All the equations for the expansion …

    vt Repository record for An application of Chebyshev polynomials to the solution of a two-dimensional elliptic boundary-value problem (opens in a new tab)

  3. The rate of decay of fresh fission products from a nuclear reactor

    … exposed 0.5 grams of U3O8 to a fast and thermal neutron flux from a TRIGA Research Reactor (Lakewood, CO) for ten minutes. The dose rate from the fission products was measured by four Mirion DMC 2000XB electronic personal dosimeters over a period of six days. The resulting dose rate with …

    colostate Repository record for The rate of decay of fresh fission products from a nuclear reactor (opens in a new tab)

  4. Neutron radiography with the VPI & SU research reactor

    … study to determine the feasibility of neutron radiography with the VPI & SU Research Reactor has been completed. Various experimental facilities of the reactor were tested to determine which gave the best beam parameters. The beam parameters considered were: 1) thermal neutron flux; 2) …

    vt Repository record for Neutron radiography with the VPI & SU research reactor (opens in a new tab)

  5. Design and characterization of a strong positron source at the MSTR beam port

    … moderation processes at the MSTR beam port. The thermal neutron flux at the beam port was determined experimentally and used in the source definition of the radiation transport simulations. The source comprised a Cd (n,γ) converter with a tungsten foil grid acting as both pair production target …

    must-thes Repository record for Design and characterization of a strong positron source at the MSTR beam port (opens in a new tab)

  6. Theoretical performance analysis of a novel hemispherical tissue equivalent proportional counter for neutron monitoring and dosimetry

    Neutron dosimetry in reactor fields is currently conducted using thermal neutron flux monitors. It has been demonstrated that Tissue Equivalent Proportional Counters (TEPCs) have the potential to improve the accuracy of neutron dosimetry in these reactor fields, and Multi-Element Tissue Equivalent …

    uoit Repository record for Theoretical performance analysis of a novel hemispherical tissue equivalent proportional counter for neutron monitoring and dosimetry (opens in a new tab)

  7. Steady and Transient Analysis of Flow and Heat Transfer in SPND Assembly

    … and heat transfer for the SPND (Self-Powered Neutron Detector) system used within the nuclear reactor core in the U.S. Evolutionary Power Reactor developed by AREVA. The SPND system is composed of six individual detectors which are used for in-core measurement of thermal neutron flux. The …

    vt Repository record for Steady and Transient Analysis of Flow and Heat Transfer in SPND Assembly (opens in a new tab)

  8. Neutronic characterization of a Molybdenum-99-producing CANDU fuel bundle and implications for reactivity-device worth and refuelling strategies

    … to their ability to be refuelled online, high thermal neutron flux and fuel-design flexibility. A Molybdenum-producing bundle (MPB) has previously been designed for that purpose and shown to be equivalent to the standard CANDU bundle (SCB) under normal, steady-state, conditions. However, before …

    uoit Repository record for Neutronic characterization of a Molybdenum-99-producing CANDU fuel bundle and implications for reactivity-device worth and refuelling strategies (opens in a new tab)

  9. Neutron Spectrum Unfolding of the University of Illinois Advanced Triga

    Made available in DSpace on 2017-07-06T18:55:48Z (GMT). No. of bitstreams: 3 Peach_Robert_O_MS.pdf: 51648898 bytes, checksum: ada2b26ac6a1e9d6af56db4ca0d2aa76 (MD5) Peach_Robert_O_MS_ABS.pdf: 422968 bytes, checksum: 98d14c3de74eb794a3a98fec459d0ce7 (MD5) license.txt: 4813 bytes, checksum: …

    uiuc Repository record for Neutron Spectrum Unfolding of the University of Illinois Advanced Triga (opens in a new tab)

  10. The noble gas record of terrestrial and meteoritic samples

    … of excess proton-rich xenon isotopes and excess neutron-rich xenon isotopes which cannot be explained by the occurrence of nuclear or fractionation processes within the meteorites.</li> <li>Possible sources suggested for this anomalous xenon cornponent are (i) xenon from a supernova explosion, …

    must-thes Repository record for The noble gas record of terrestrial and meteoritic samples (opens in a new tab)