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Showing 1 to 20 of 22 for “"neutron absorption"”.

  1. Neutron Absorption Self-Shielding Factors in Activation Analysis

    Made available in DSpace on 2017-07-06T18:49:04Z (GMT). No. of bitstreams: 3 Kirstein_Erik_S_MS.pdf: 34553387 bytes, checksum: fde921d66760107ce07c13230d4cbf57 (MD5) Kirstein_Erik_S_MS_ABS.pdf: 526029 bytes, checksum: 7f7a393a4aa77b7f53ed964a9bb6162b (MD5) license.txt: 4813 bytes, checksum: …

    uiuc Repository record for Neutron Absorption Self-Shielding Factors in Activation Analysis (opens in a new tab)

  2. Numerical simulation of nuclear reactor isotope depletion

    … the depletion calculations and used a simplified neutron flux equation. Nuclide data like cross-sections and fission products were read in from ENDF format files that have undergone pre-processing. To solve the more than 500 simultaneous differential equations that describe the varying isotopic …

    cape-town Repository record for Numerical simulation of nuclear reactor isotope depletion (opens in a new tab)

  3. Estudo do processamento termomecânico de liga experimental de zircônio e seu efeito nas propriedades mecânicas e formação de hidretos

    … resistance, thermal conductivity and low neutron absorption. The interaction with hydrogen during the operation of the reactor leads to the formation of hydrides, dependent on the presence of crystalline discontinuities and on the texture of the material. This work aimed to validate the …

    brazil-uerj Repository record for Estudo do processamento termomecânico de liga experimental de zircônio e seu efeito nas propriedades mecânicas e formação de hidretos (opens in a new tab)

  4. Critical assessment of thorium reactor technology

    … Thorium itself offers a significantly greater neutron absorption cross-section than uranium at thermal energies, resulting in greater efficiency and smaller geometries. Certain thorium-based fuels can also significantly reduce proliferation by denaturing the thorium fuel cycle product U-233 …

    mit Repository record for Critical assessment of thorium reactor technology (opens in a new tab)

  5. Epithermal neutron activation analysis of short-lived radionuclides using a pneumatic transport system and a pulsed D-T neutron generator

    … produced during irradiation by a D-T neutron generator was constructed. Target samples of indium, palladium, and germanium were irradiated by the neutron generator embedded in a graphite monolith to produce epithermal activation products. The three radioisotopes of interest are …

    uiuc Repository record for Epithermal neutron activation analysis of short-lived radionuclides using a pneumatic transport system and a pulsed D-T neutron generator (opens in a new tab)

  6. Feasibility study of compact Neutron Resonance Transmission Analysis using a linac, a fusion-based neutron generator, and an isotopic source

    … nuclear materials in a black box target. Neutron Resonance Transmission Analysis (NRTA) is a spectroscopic technique which uses resonant neutron absorption to identify isotopic compositions. Previous NRTA experiments have used expensive beam line facilities with kilometer-long …

    mit Repository record for Feasibility study of compact Neutron Resonance Transmission Analysis using a linac, a fusion-based neutron generator, and an isotopic source (opens in a new tab)

  7. Numerical modeling study of a neutron depth profiling (NDP) system for the Missouri S&T reactor

    <p>”For decades, Neutron Depth Profiling has been used for the non-destructive analysis and quantification of boron in electronic materials and lithium in lithium ion batteries. NDP is one of the few non-destructive analytical techniques capable of measuring the depth profiles of light elements to …

    must-thes Repository record for Numerical modeling study of a neutron depth profiling (NDP) system for the Missouri S&T reactor (opens in a new tab)

  8. Capture cross sections in the KeV region

    Many workers have attempted to determine neutron absorption cross sections and average resonance parameters with varying degrees of success. Values of the latter parameters for a given isotope often vary as much as a factor of two or three from one worker to another. This dissertation is an attempt …

    vt Repository record for Capture cross sections in the KeV region (opens in a new tab)

  9. Industrial applications of photonuclear resonance excitation

    … achieved using bremsstrahlung, in contrast with neutron based approaches where suitable neutron sources of sufficient intensity for these applications are lacking. In order to design a system for creating nuclear isomers using photons, the resonant photon absorption isomeric excitation cross …

    mit Repository record for Industrial applications of photonuclear resonance excitation (opens in a new tab)

  10. Measurement and analysis of the resolved resonance cross sections of the natural hafnium isotopes

    … is a ductile metallic element with a large neutron absorption cross section. It can be used in reactor control rods to regulate the fission process. The NEA High Priority Request List for nuclear data presents a need for improved characterisation of the hafnium cross section in the resolved …

    birmingham Repository record for Measurement and analysis of the resolved resonance cross sections of the natural hafnium isotopes (opens in a new tab)

  11. Thorium-based mixed oxide fuel in a pressurized water reactor: A feasibility analysis with MCNP

    … performed for the Portable Spectroscopic Fast Neutron Probe (N-Probe), which can be used for spent fuel interrogation. Also, a Canberra <sup>3</sup>He neutron detector's dead-time was estimated using a combination of subcritical assembly measurements and MCNP simulations. Next, a multitude of …

    must-thes Repository record for Thorium-based mixed oxide fuel in a pressurized water reactor: A feasibility analysis with MCNP (opens in a new tab)

  12. Engineering design of a fission converter-based epithermal beam for neutron capture therapy

    … high intensity and low contamination epithermal neutron beams, for boron neutron capture therapy research and for routine treatment if this becomes a successful modality for treating cancers. A fission converter based design for high performance epithermal neutron beam was developed at the …

    mit Repository record for Engineering design of a fission converter-based epithermal beam for neutron capture therapy (opens in a new tab)

  13. High-Resolution Characterization of Micro-Scale Crack Tip Fields in Zirconium

    … core components owing to their low thermal neutron absorption cross-section and adequate mechanical and corrosion properties. To ensure the sustainable design and safe operation of nuclear reactors, understanding the failure mechanisms of these components is essential. In CANDU (CANada …

    queens Repository record for High-Resolution Characterization of Micro-Scale Crack Tip Fields in Zirconium (opens in a new tab)

  14. Mode I Fracture Testing on Zirconium Foils Under Plane-stress Condition

    … due to their good mechanical properties and low neutron-absorption cross-section. Especially for CANada Deuterium Uranium (CANDU) reactors, zirconium alloys serve as the main structural material for fuel channels. In order to ensure such Zr components operate safely, fracture analysis of Zr …

    queens Repository record for Mode I Fracture Testing on Zirconium Foils Under Plane-stress Condition (opens in a new tab)

  15. Amorphous hydrogenated boron carbide for solid-state direct-conversion thermal neutron detection

    … (a-BC:H) is one of a very limited number of neutron-sensitive materials. It has been studied over the last three decades for solid-state thermal neutron detection due to its high resistivity, moderate bandgap, high neutron absorption cross-section, and high stability under harsh physical and …

    umkc Repository record for Amorphous hydrogenated boron carbide for solid-state direct-conversion thermal neutron detection (opens in a new tab)

  16. Reactor physics considerations for implementing silicon carbide cladding into a PWR environment

    … little reaction with steam, and more favorable neutron absorption. To evaluate the feasibility of longer fuel cycles and higher power density in SiC clad fuel, a core design study was completed with uranium dioxide fuel and SiC cladding in a standard, Westinghouse 4-loop PWR. NRC-limited values …

    mit Repository record for Reactor physics considerations for implementing silicon carbide cladding into a PWR environment (opens in a new tab)

  17. Investigation of the mechanical behavior of rim/blister structure hydride phases in Zircaloy-4 by utilizing high energy synchrotron X-ray diffraction

    … properties, corrosion resistance and low thermal neutron absorption cross-section. However, in service absorption of hydrogen by Zircaloy-4 (Zry-4) cladding is potentially problematic. One issue is the delayed hydride cracking (DHC) phenomenon which occurs during storage of used nuclear fuel …

    uiuc Repository record for Investigation of the mechanical behavior of rim/blister structure hydride phases in Zircaloy-4 by utilizing high energy synchrotron X-ray diffraction (opens in a new tab)

  18. Machine-learning models and shielding materials for radiation protection of patients and personnel in ion therapy

    … detecting and discriminating both gamma rays and neutrons to perform real-time range verification. After thorough experimental characterization of the stilbene-d12 light-output response, we used Monte Carlo simulation to demonstrate that the fall-off of the neutron flux remotely measured by the …

    uiuc Repository record for Machine-learning models and shielding materials for radiation protection of patients and personnel in ion therapy (opens in a new tab)

  19. Silicon carbide performance as cladding for advanced uranium and thorium fuels for light water reactors

    … well as lower thermal expansion, creep rate, and neutron absorption cross-section. However, under irradiation, the thermal conductivity of SiC is degraded considerably. Furthermore, lack of creep down towards the fuel causes the fuel-cladding gap and gap thermal resistance to stay relatively large …

    mit Repository record for Silicon carbide performance as cladding for advanced uranium and thorium fuels for light water reactors (opens in a new tab)

  20. Application of advanced fuel concepts for use in innovative pressurized water reactors

    … a core with SiC CMC cladding, due to its lower neutron absorption compared to Zircaloy. The thorium system was also better from a non-proliferation viewpoint, resulting in less fissile mass at discharge and more fissile mass burned over an assembly's lifetime. A limited safety comparison was …

    mit Repository record for Application of advanced fuel concepts for use in innovative pressurized water reactors (opens in a new tab)

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