Download or read book Enhancement of the Thermal Neutron Flux in the Central Irradiation Facility of the Ohio State University Research Reactor written by Tze-Hore Howard Liu and published by . This book was released on 1979 with total page 288 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Specification of the Neutron Environment in the Central Irradiation Facility of the Ohio State University Research Reactor written by Brian K. Hajek and published by . This book was released on 1972 with total page 134 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Design and Development of an External Fast Neutron Beam Facility at the Ohio State University Research Reactor written by Andrew M. Zapp and published by . This book was released on 2019 with total page 112 pages. Available in PDF, EPUB and Kindle. Book excerpt: The ability of the Ohio State University Research Reactor, OSURR, to conduct experiments from the generation of the neutron flux is important in conducting research by the University and external entities that require a flux of this magnitude. In particular, research involving a fast neutron flux is of interest due to the different interactions fast neutrons have as opposed to thermal neutrons. The OSURR is able to operate up to 500 kW, which creates a neutron flux in the order of 1013 n/cm2-s. Currently, Beam Port 2 provides a thermal neutron beam profile of 30 mm in diameter for experimentation such as neutron depth profiling, activation analysis, and evaluation of radiation damage to electronics. Beam Port 1 uses a sample area located adjacent and perpendicular to the fuel plates of the reactor for in-core irradiation. During experimentation, the remainder of Beam Port 1 must be plugged with removable concrete shielding to prevent radiation exposure that can be upwards of 1x104 rem/hr. The upgrade to Beam Port 1 consists of a collimator to shape the neutron flux from the reactor into a beam of fast neutrons, similar in diameter to Beam Port 2, in order to irradiate samples external to the reactor. In addition, mobile external shielding is designed to prevent exceeding the exposure limits of 5 rem/yr when the facility is in use. With this upgrade the research reactor has the ability to conduct simultaneous experiments with a fast and thermal neutron beam, external to the biological shielding, without releasing any harmful exposure.
Download or read book The Design of a Cell Irradiation Facility Located in the Thermal Column of the Ohio State University Research Reactor written by Hassan Saeed Basha and published by . This book was released on 1989 with total page 166 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Minimum Critical Mass and Uniform Thermal Neutron Core Flux in an Experimental Reactor written by J. W. Morfitt and published by . This book was released on 1955 with total page 170 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Characteristics of the LPTR Fast Neutron Irradiation Facility written by Garth E. Cummings and published by . This book was released on 1969 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Report on Calculations of the Neutron Flux Distribution in the Reactor Tank the Reflectors and Thermal Column of the Uranium Pile at Kjeller written by N. Holt and published by . This book was released on 1951 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book A Neutronic Study of an Accelarator Based Thermal Neutron Irradiation Facility for Boron Neutron Capture Therapy written by Tanxia Qu and published by . This book was released on 1989 with total page 200 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Calculation of Thermal Neutron Fluxes in Primary Shields written by D. C. Anderson and published by . This book was released on 1959 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Measurement of the Neutron Spectra in the Beam Ports and Thermal Column of the Ohio State University Research Reactor written by Nicholas C. Horning and published by . This book was released on 1976 with total page 188 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book A Determination of the Neutron Temperature at the Center of the Thermal Test Reactor written by G. B. Gavin and published by . This book was released on 1954 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Neutron Flux Enhancement in the NRAD Reactor written by and published by . This book was released on 1988 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: In 1987 a series of experiments were conducted at the NRAD reactor facility at Argonne National Laboratory - West (ANL-W) to investigate the possibility of increasing the thermal neutron content at the end of the reactor's east beam tube through the use of hydrogenous flux traps. It was desired to increase the thermal flux for a series of experiments to be performed in the east radiography cell, in which the enhanced flux was required in a relatively small volume. Hence, it was feasible to attempt to focus the cross section of the beam to a smaller area. Two flux traps were constructed from unborated polypropylene and tested to determine their effectiveness. Both traps were open to the entire cross-sectional area of the neutron beam (as it emerges from the wall and enters the beam room). The sides then converged such that at the end of the trap the beam would be 'focused' to a greater intensity. The differences in the two flux traps were primarily in length, and hence angle to the beam as the inlet and outlet cross-sectional areas were held constant. It should be noted that merely placing a slab of polypropylene in the beam will not yield significant multiplication as neutrons are primarily scattered away.
Download or read book Updated Flux Information for Neutron Scattering and Irradiation Facilities at the BNL High Flux Beam Reactor written by and published by . This book was released on 1997 with total page 3 pages. Available in PDF, EPUB and Kindle. Book excerpt: The HFBR is a heavy water, D2O, cooled and moderated reactor with twenty-eight fuel elements containing a maximum of 9.8 kilograms of 235U. While most reactors attempt to minimize the escape of neutrons from the core, the HFBR's D2O design allows the thermal neutron flux to peak in the reflector region and maximizes the number of thermal neutrons available to nine horizontal external beams, H-1 to H-9, used for neutron scattering and capture reactions, supporting physics, chemistry and biology experiments. All horizontal beam tubes were built tangential to the direction of the emerging neutrons, except for the H-2 beam tube, which looks directly at the core and has been used for neutron cross section measurements utilizing fast neutrons and for the TRISTAN fission product studies. In recent years, there have been some beam modifications and new instrumentation introduced at the HFBR. A high resolution neutron powder diffractometer instrument is now operating with a resolution of 5 x 10−4 at horizontal beam line H-1. To study scattering from liquid surfaces, a neutron reflection spectrometer was introduced on the CNF beam line at H-9. In the past year, a fourth beam line has been added to the CNF line at H-9. The existing beam plug at the H-6 beam line has recently been removed and a new plug, which will feature super mirrored surfaces, is now being installed. Last year, the vertical beam thimble, V-13, a fixed port filled with thirty year old samples used for HFBR material surveillance studies was replaced by a new thimble and charging station at the core edge creating an irradiation facility to substitute for the original V-13. A neutron dosimetry program has begun to measure and calculate the energy dependent neutron and gamma ray flux densities and/or dose rates at horizontal beam lines and vertical irradiation thimbles.
Download or read book Design of an In core Fission Spectrum Neutron Irradiation Facility with Pneumatic Sample Transfer at a Research Reactor written by Brandon Alexander De Luna and published by . This book was released on 2019 with total page 684 pages. Available in PDF, EPUB and Kindle. Book excerpt: The objective of this thesis was to provide instruction on the design, optimization and construction of a fast neutron irradiation facility with pneumatic sample transfer at the Nuclear Engineering Teaching Lab (NETL) reactor core. This facility will be used for fast neutron activation analysis and fast neutron fission in uranium and plutonium samples. Various materials and geometric designs were researched and modeled in Monte Carlo Neutral Particle (MCNP) code for the filtration of thermal neutrons from the NETL reactor core. The approach to these models were described as well as the subsequent processes in yielding the finalized design. The model geometry was recreated in SCALE to provide estimations for expected fission product activities. The design that was built was based off a layered cylindrical format that was placed inside a modified 3-element (EL) container. This container was created to fit into the 3-EL irradiation position of the core. The design balances the need to maintain high total neutron flux with the careful shaping of a neutron spectrum to be as close to the Watt fission spectrum as possible. The models indicated that the thermal+epithermal neutron flux was reduced by five orders of magnitude while leaving the fast neutron flux virtually untouched. That value was tallied after the reactor core flux is shaped by the neutron absorbing materials. The fast:(thermal+epithermal) flux ratio should exceed 100:1 with an integrated fast flux value (defined > 0.001 MeV) of at least 7.8 x 1011 n cm−2 s−1. The calculated activity from the irradiation of 10 mg Pu via SCALE was determined to be 94.97 MBq
Download or read book Design Construction and Characterization of a Fast Neutron Beam Port Facility at the University of Texas at Austin TRIGA Reactor written by Daniel Caldwell Barron and published by . This book was released on 2018 with total page 518 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book Neutron Irradiation of Seeds III written by International Atomic Energy Agency and published by . This book was released on 1972 with total page 148 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Neutron Flux Determination in Washington State University Reactor Irradiation Facilities written by Waldemar F. Hendrickson and published by . This book was released on 1964 with total page 54 pages. Available in PDF, EPUB and Kindle. Book excerpt:
