Author: Hadj Slimane CherifPublisher:
ISBN:
Category :
Languages : en
Pages : 76
Book Description
Thermal Neutron Spectrum from the Triga Mark III Reactor
Author: Hadj Slimane CherifAn Easier Way to a Harder Spectrum
Author: Michael T. Pierce (Jr.)Publisher:
ISBN:
Category :
Languages : en
Pages : 998
Book Description
The TRIGA Mark II research reactor has a flux spectrum with a predominance of thermal neutrons. While most research can be conducted using this thermal neutron flux, an exclusively fast neutron flux is preferred for some experiments, such as radiation damage studies. Although fast neutron flux spectrums are available using fast reactors or neutron generators, only a few fast reactors are currently in operation and neutron generators tend to have low fluxes. As a result, this report evaluated the possibility of generating a fast neutron flux spectrum in a thermal reactor through the use of an irradiator consisting of layers of uranium, boron, and cadmium. Simulations using Monte Carlo N-Particle Code (MCNP) determined that thin layers of these materials in an irradiator inserted into the 3-Element Facility of the UT-Austin TRIGA reactor will generate a fast neutron flux spectrum with negligible thermal flux and where over 91% of the total flux consists of neutrons with energy greater than 10 keV. Further research is recommended to calculate heat dissipation and to determine the reactivity worth of the irradiator
Neutron Flux and Spectra Measurements in the Void Tank of the TRIGA Mark-F Reactor
Author: K. C. HumpherysPublisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 22
Book Description
Design, Construction, and Characterization of a Fast Neutron Beam Port Facility at the University of Texas at Austin TRIGA Reactor
Author: Daniel Caldwell BarronPublisher:
ISBN:
Category :
Languages : en
Pages : 518
Book Description
A fast neutron irradiation facility has been designed, modeled, and constructed in the beam port 4 facility at The University of Texas at Austin’s TRIGA Mark-II Reactor. This facility targets the Watt-fission neutron spectrum in a controlled environment by reducing the present thermal and epithermal flux while preserving the fast neutron flux. The present facility will open new avenues in nuclear non-proliferation for fast-fission yields in addition to measuring radionuclide migration. The filter system was designed using MCNP and Solidworks and consists of a lead plug to stop gamma-rays, filter elements of natural boron and 96% enriched B10, collimation elements of borated polyethylene and natural boron, and an exit filter of boron nitride. A beam stop was constructed to reduce the ambient dose rate using borated paraffin wax, polyethylene, cadmium, and lead. Sensitivity studies were performed to configure an economic facility by optimizing the amounts and configurations of materials used in the filter. The filter is modular to allow for rearrangement of elements and the ability to change the materials used as needed should higher efficiencies be desired or a higher total flux. Initial results indicate the facility produces a 10 cm diameter beam with an integrated flux of 6.63x105 n/cm2/s at a reactor power of 950 kW and resembles the Watt-fission spectrum well with a slightly elevated epithermal neutron flux. The fast neutron flux above 0.1 MeV constitutes 98.77% of the total flux and the thermal neutron flux only 0.0014% of the total flux. STAYSL PNNL was used to unfold the neutron spectrum from 9 measurable reactions in 5 flux foils. Results suggest that the fast neutron flux is higher than anticipated in all STAYSL runs although the total flux is lower than anticipated.
History, Development and Future of TRIGA Research Reactors
Author: Publisher:
ISBN: 9789201281197
Category : Nuclear reactors
Languages : en
Pages : 131
Book Description
Neutron Thermalization and Reactor Spectra
Author: Fast Neutron Spectrum of the Afrri Triga Reactor
Author: A. Edward ProfioPublisher:
ISBN:
Category : Fast neutrons
Languages : en
Pages : 0
Book Description
The angular flux spectrum was measured in a 43 cm sphere filled with the mixture ZrH1.9O0.3Fe0.1A10.05B0.01' representing the approximate homogenized TRIGA reactor core composition (without uranium, and with boron added for thermal neutron absorption). The sphere was reflected with 5.08 cm of water. A 7.6 cm diameter depleted uranium target embedded at the center, excited by a 20 nsec pulsed electron beam for a Linac, was the neutron source for the time-of-flight experiment (50 meter flight distance). Detectors were a 5 by 5 cm liquid scintillator for spectra from 0.4-14 MeV, and a boron capture gamma ray detector for 0.1-0.5 MeV. Measurements were made at 7.6 cm penetration (0 and 51 degrees to the radius vector), at the core-reflector interface, and at the surface of the reflector (0 and 46 degrees). Calculations of the spectrum in the experimental assembly were made with the GAPLSN S sub n code in S8, with 20-group P3 cross sections from the GAM-II code. Comparisons between calculations and experiment were made to decide on the angular mesh, order of anisotropic scattering approximation, energy grouping, and cross sections for a similar calculation of the critical TRIGA reactor spectrum. Results of the calculated cylindrical geometry, P3, S8 angular flux spectrum and total leakage spectrum at the surface of the reflector are tabulated. (Author).
Neutron Spectrum Unfolding in Three Irradiation Channels of the JSI TRIGA Mark II Reactor with the GRUPINT Code
Author: Vladimir RadulovićA THERMAL NEUTRON SPECTRUM MEASURED BY A CRYSTAL SPECTROMETER
Author: Format and Content of the Safety Analysis Report for Nuclear Power Plants
Author: International Atomic Energy AgencyPublisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 98
Book Description
This Safety Guide is intended primarily for use with land based stationary thermal nuclear power plants but it may, in parts, have a wider applicability to other nuclear facilities. It provides recommendations and guidance on the possible format and content of a SAR in support of a request to the State regulatory body for authorization to construct and or operate a nuclear power plant. As such, it contains recommendations on meeting the requirements of Safety guide GS-R-1 "Legal and governmental infrastructure for nuclear, radioactive waste and transport safety" (2000, ISBN 9201008007)