Download or read book Thermal Neutron Beam Design for Triga Reactor at Berkeley Campus written by and published by . This book was released on 1967 with total page 220 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Thermal Neutron Spectrum from the Triga Mark III Reactor written by Hadj Slimane Cherif and published by . This book was released on 1967 with total page 76 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Design and Construction of a Cold Neutron Source for Use in the Cornell University Triga Reactor written by Lydia Jane Young and published by . This book was released on 1983 with total page 282 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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 Beam Design Development and Performance for Neutron Capture Therapy written by Otto K. Harling and published by Springer Science & Business Media. This book was released on 2013-03-08 with total page 340 pages. Available in PDF, EPUB and Kindle. Book excerpt: For this Workshop, the organizers have attempted to invite experts from all known centers which are engaged in neutron beam development for neutron capture therapy. The Workshop was designed around a series of nineteen invited papers which dealt with neutron source design and development and beam characterization and performance. Emphasis was placed on epithermal beams because they offer clinical advantages and are more challenging to implement than thermal beams. Fission reactor sources were the basis for the majority of the papers; however three papers dealt with accelerator neutron sources. An additional three invited papers provided a summary of clinical results of Ncr therapy in Japan between 1968 and 1989 and overviews of clinical considerations for neutron capture therapy and of the status of tumor targeting chemical agents for Ncr. Five contributed poster papers dealing with NCT beam design and performance were also presented. A rapporteurs' paper was prepared after the Workshop to attempt to summarize the major aspects, issues, and conclusions which resulted from this Workshop. Many people contributed to both the smooth functioning of the Workshop and to the preparation of these proceedings. Special thanks are reserved for Ms. Dorothy K.

Download or read book Design Construction and Characterization of an External Neutron Beam Facility at The Ohio State University Nuclear Reactor Laboratory written by Danyal J. Turkoglu and published by . This book was released on 2012 with total page 93 pages. Available in PDF, EPUB and Kindle. Book excerpt: Abstract: The objective of this research was to bring a thermal neutron beam facility to the Ohio State University Nuclear Reactor Laboratory for the purposes of neutron-based research. The neutron beam is extracted from the reactor core through a neutron collimator emplaced in Beam Port #2, the radial beam port facing the core at a 30° angle. The collimator is an aluminum tube containing components designed to filter and shape the neutron beam. The filters are poly-crystalline bismuth (10.16 cm thickness, 12.7 cm diameter) for significantly reducing gamma ray content and single-crystal sapphire (12.7 cm thickness, 10.16 cm diameter) for preferentially passing thermal neutrons while scattering more energetic neutrons out of the beam. The thermal neutron beam is defined by multiple 3.0 cm diameter apertures in borated aluminum. Apertures in polyethylene-based disks and in Pb disks provide shielding for fast neutrons and gamma rays, respectively, in the neutron collimator. Characterization of the beam was performed using foil activation analysis to find the neutron flux and a low-cost digital neutron imaging apparatus to "see" the beam profile. The neutron collimator delivers the filtered thermal neutron beam with a 3.5 cm diameter umbra and a thermal neutron equivalent flux of (8.55 +̲ 0.19) x 106 cm−2s−1 at 450 kW reactor power (90% of rated limit) to the sample location. The beam is highly thermalized with a cadmium ratio of 266 +̲ 13. The facility was designed for neutron depth profiling, a nondestructive analytical technique for finding the concentration versus depth in the near surface (tens of microns) for isotopes that undergo charged particle emitting reactions, such as 10B(n, 4He)7Li, 6Li (n, 3H)4He, and 3He (n, 1H)3H, to name a few.

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 Commencement programme written by University of California, Berkeley and published by . This book was released on 1968 with total page 600 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Performance of a New Composite Single Crystal Filtered Thermal Neutron Beam for Neutron Capture Therapy Research at the University of Missouri written by and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The University of Missouri (MU) Institute for Nano and Molecular Medicine, the Idaho National Laboratory (INL) and the University of Missouri Research Reactor (MURR) have undertaken a new collaborative research initiative to further the development of improved boron delivery agents for BNCT. The first step of this effort has involved the design and construction of a new thermal neutron beam irradiation facility for cell and small-animal radiobological research at the MURR. In this paper we present the beamline design with the results of pertinent neutronic design calculations. Results of neutronic performance measurements, initiated in February 2008, will also be available for inclusion in the final paper. The new beam will be located in an existing 152.4 mm (6') diameter MURR beam tube extending from the core to the right in Figure 1. The neutron beam that emanates from the berylium reflector around the reactor is filtered with single-crystal silicon and single-crystal bismuth segments to remove high energy, fission spectrum neutrons and reactor gamma ray contamination. The irradiation chamber is downstream of the bismuth filter section, and approximately 3.95 m from the central axis of the reactor. There is sufficient neutron flux available from the MURR at its rated power of 10 MW to avoid the need for cryogenic cooling of the crystals. The MURR operates on average 150 hours per week, 52 weeks a year. In order to take advantage of 7800 hours of operation time per year the small animal BNCT facility will incorparate a shutter constucuted of boral, lead, steel and polyethylene that will allow experimenters to access the irradiation chamber a few minutes after irradiation. Independent deterministic and stochastic models of the coupled reactor core and beamline were developed using the DORT two-dimensional radiation transport code and the MCNP-5 Monte Carlo code, respectively. The BUGLE-80 47-neutron, 20-gamma group cross section library was employed for the DORT computations, in keeping with previous practice for analysis of a number of other NCT neutron facilities worldwide. The standard ENDF/B Version 6.8 cross section libraries were used with MCNP, except that special calculated cross section sets for the single-crystal bismuth and silicon filters in the MCNP calculations were provided to MU and INL specifically for this study by the Korean Atomic Energy Research Institute and, independently, by North Carolina State University. Cross sections for the amorphous bismuth and silicon files on the BUGLE-80 library used with DORT were modified to account for the single-crystal form of these materials using correction factors computed using MCNP. A number of parameter studies were conducted, independently varying the thicknesses of the silicon and bismuth filter sections to find an optimum that maximizes the thermal neutron flux while maintaining the fast-neutron and gamma components of the beam within acceptable ranges. Both the DORT and MCNP beamline optimization computations led to the conclusion that the silicon filtering section should be approximately 55 cm in thickness and the bismuth section should be 8 cm in thickness. The total estimated thermal neutron flux delivered to the irradiation location by the filtered beam, integrated to 0.414 eV, is approximately 9.0 x 108 neutrons/cm2-s. The calculations also yielded an epithermal and fast-neutron kerma of approximately 1.0 x 10-11 cGy-cm2.

Download or read book Energy Research Abstracts written by and published by . This book was released on 1987 with total page 648 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1983 with total page 748 pages. Available in PDF, EPUB and Kindle. Book excerpt: Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.

Download or read book Investigation of a Flux Trap for Enhanced Thermal Neutron Production in a TRIGA Nuclear Reactor written by Ross Job Thompson and published by . This book was released on 1982 with total page 138 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1974 with total page 580 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Neutron Diffusion Calculation for the Berkeley Research Reactor written by Howard Martin Johnson and published by . This book was released on 1967 with total page 88 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Experimental Neutron Thermalisation written by Peter A. Egelstaff and published by Pergamon. This book was released on 1969 with total page 424 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Initial Experimental Verification of the Neutron Beam Modeling for the LBNL BNCT Facility written by and published by . This book was released on 1999 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: In preparation for future clinical BNCT trials, neutron production via the 7Li(p, n) reaction as well as subsequent moderation to produce epithermal neutrons have been studied. Proper design of a moderator and filter assembly is crucial in producing an optimal epithermal neutron spectrum for brain tumor treatments. Based on in-phantom figures-of-merit, desirable assemblies have been identified. Experiments were performed at the Lawrence Berkeley National Laboratory's 88-inch cyclotron to characterize epithermal neutron beams created using several microampere of 2.5 MeV protons on a lithium target. The neutron moderating assembly consisted of Al/AlF3 and Teflon, with a lead reflector to produce an epithermal spectrum strongly peaked at 10-20 keV. The thermal neutron fluence was measured as a function of depth in a cubic lucite head phantom by neutron activation in gold foils. Portions of the neutron spectrum were measured by in-air activation of six cadmium-covered materials (Au, Mn, In, Cu, Co, W) with high epithermal neutron absorption resonances. The results are reasonably reproduced in Monte Carlo computational models, confirming their validity.

Download or read book written by and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: