Download or read book Neutronic Design of a Low Enriched Uranium U3Si2 Al Core for the Ohio State University Research Reactor written by M. D. Seshadri and published by . This book was released on 1988 with total page 176 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Three dimensional Neutronic Calculations for the Low Enriched Uranium Conversion upgrade of The Ohio State University Research Reactor written by Hikmet Selli Aybar and published by . This book was released on 1987 with total page 190 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Advances in Neutron Capture Therapy written by R.F. Barth and published by Springer Science & Business Media. This book was released on 2012-12-06 with total page 776 pages. Available in PDF, EPUB and Kindle. Book excerpt: Binary systems for the treatment of cancer potentially are among the most attractive of the new therapeutic modalities that currently are under investigation. The basicconcept is to selectivelydestroy malignantcells whileconcomitantlysparing normal tissue. Neutron capture therapy (NCT) is the binary system that has been the subject of the Fifth International Symposium on Neutron Capture Therapy, which was held September13-17, 1992, in Columbus, Ohio, undertheauspicesoftheInternational Society for Neutron Capture Therapy. Its objective was to bring together researchers from throughout the world and to provide a forum at which they could present the latest advances in the development of Neutron capture therapy. Neutron capture therapy has largely, but not exclusively, focused on the use of boron-10 as the target nuclide. Boron neutron capture therapy (BNCT) is based on the nuclear reaction that occurs when the stable isotope, boron-10, absorbs low-energy non ionizing thermal neutrons to yield alphaparticles and recoiling lithium-7 nuclei. The size and energy of these high linear energy transfer (LET) particles result in their being confined largely to the cells in which the capture reaction occurs. For BNCT to be successful, a sufficient numberof I~atoms mustbe localized within neoplastic cells, and enough thermal neutrons must be delivered and absorbed by the I~ to produce a lethal 1~(n,QVLi reaction. Two major problems must be surmounted.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1990 with total page 852 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Assessing the Impact of Low Enriched Uranium Core Conversion on the Utilization of Low Power Reactors in Boron Neutron Capture Therapy Research written by Lisa Ann Heimberger and published by . This book was released on 1990 with total page 138 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Conversion of Research and Test Reactors to Low enriched Uranium LEU Fuel written by United States. Congress. House. Committee on Science and Technology. Subcommittee on Energy Development and Applications and published by . This book was released on 1985 with total page 1968 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Transactions of the American Nuclear Society written by American Nuclear Society and published by . This book was released on 1992 with total page 614 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Low Enriched Uranium Fuel Design with Two Dimensional Grading for the High Flux Isotope Reactor written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: An engineering design study of the conversion of the High Flux Isotope Reactor (HFIR) from high-enriched uranium (HEU) to low-enriched uranium (LEU) fuel is ongoing at Oak Ridge National Laboratory. The computational models developed during fiscal year 2010 to search for an LEU fuel design that would meet the requirements for the conversion and the results obtained with these models are documented and discussed in this report. Estimates of relevant reactor performance parameters for the LEU fuel core are presented and compared with the corresponding data for the currently operating HEU fuel core. The results obtained indicate that the LEU fuel design would maintain the current performance of the HFIR with respect to the neutron flux to the central target region, reflector, and beam tube locations under the assumption that the operating power for the reactor fueled with LEU can be increased from the current value of 85 MW to 100 MW.
Download or read book Two region Experiments in Slightly Enriched Water moderated Uranium and Uranium Dioxide Lattices written by G. G. Smith and published by . This book was released on 1958 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Neutronics and Thermal Hydraulics Study for Using a Low Enriched Uranium Core in the Advanced Test Reactor 2008 Final Report written by and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Test Reactor (ATR) is a high power density and high neutron flux research reactor operating in the United States. Powered with highly enriched uranium (HEU), the ATR has a maximum thermal power rating of 250 MWth. Because of the large test volumes located in high flux areas, the ATR is an ideal candidate for assessing the feasibility of converting an HEU driven reactor to a low-enriched core. The present work investigates the necessary modifications and evaluates the subsequent operating effects of this conversion. A detailed plate-by-plate MCNP ATR 1/8th core model was developed and validated for a fuel cycle burnup comparison analysis. Using the current HEU U 235 enrichment of 93.0 % as a baseline, an analysis was performed to determine the low-enriched uranium (LEU) density and U-235 enrichment required in the fuel meat to yield an equivalent K-eff versus effective full power days (EFPDs) between the HEU and the LEU cores. The MCNP ATR 1/8th core model was used to optimize the U 235 loading in the LEU core, such that the differences in K-eff and heat flux profiles between the HEU and LEU cores were minimized. The depletion methodology MCWO was used to calculate K-eff versus EFPDs in this paper. The MCWO-calculated results for the LEU demonstrated adequate excess reactivity such that the K-eff versus EFPDs plot is similar to the ATR reference HEU case study. Each HEU fuel element contains 19 fuel plates with a fuel meat thickness of 0.508 mm (20 mil). In this work, the proposed LEU (U-10Mo) core conversion case with nominal fuel meat thickness of 0.330 mm (13 mil) and U-235 enrichment of 19.7 wt% is used to optimize the radial heat flux profile by varying the fuel meat thickness from 0.191 mm (7.0 mil) to 0.330 mm (13.0 mil) at the inner 4 fuel plates (1-4) and outer 4 fuel plates (16-19). A 0.8g of Boron-10, a burnable absorber, was added in the inner and outer plates to reduce the initial excess reactivity, and the peak to average ratio of the inner/outer heat flux more effectively. Because the B-10 (n, a) reaction will produce Helium-4 (He-4), which might degrade the LEU foil type fuel performance, an alternative absorber option is proposed. The proposed LEU case study will have 6.918 g of Cadmium (Cd) mixed with the LEU at the inner 4 fuel plates (1-4) and outer 4 fuel plates (16-19) as a burnable absorber to achieve peak to average ratios similar to those for the ATR reference HEU case study.
Download or read book Analysis of the TREAT LEU Conceptual Design written by and published by . This book was released on 2016 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Analyses were performed to evaluate the performance of the low enriched uranium (LEU) conceptual design fuel for the conversion of the Transient Reactor Test Facility (TREAT) from its current highly enriched uranium (HEU) fuel. TREAT is an experimental nuclear reactor designed to produce high neutron flux transients for the testing of reactor fuels and other materials. TREAT is currently in non-operational standby, but is being restarted under the U.S. Department of Energy's Resumption of Transient Testing Program. The conversion of TREAT is being pursued in keeping with the mission of the Department of Energy National Nuclear Security Administration's Material Management and Minimization (M3) Reactor Conversion Program. The focus of this study was to demonstrate that the converted LEU core is capable of maintaining the performance of the existing HEU core, while continuing to operate safely. Neutronic and thermal hydraulic simulations have been performed to evaluate the performance of the LEU conceptual-design core under both steady-state and transient conditions, for both normal operation and reactivity insertion accident scenarios. In addition, ancillary safety analyses which were performed for previous LEU design concepts have been reviewed and updated as-needed, in order to evaluate if the converted LEU core will function safely with all existing facility systems. Simulations were also performed to evaluate the detailed behavior of the UO2-graphite fuel, to support future fuel manufacturing decisions regarding particle size specifications. The results of these analyses will be used in conjunction with work being performed at Idaho National Laboratory and Los Alamos National Laboratory, in order to develop the Conceptual Design Report project deliverable.
Download or read book Design Study for a Low enriched Uranium Core for the High Flux Isotope Reactor Annual Report for FY 2007 written by and published by . This book was released on 2007 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report documents progress made during fiscal year 2007 in studies of converting the High Flux Isotope Reactor (HFIR) from highly enriched uranium (HEU) fuel to low enriched uranium fuel (LEU). Conversion from HEU to LEU will require a change in fuel form from uranium oxide to a uranium-molybdenum alloy. A high volume fraction U/Mo-in-Al fuel could attain the same neutron flux performance as with the current, HEU fuel but materials considerations appear to preclude production and irradiation of such a fuel. A diffusion barrier would be required if Al is to be retained as the interstitial medium and the additional volume required for this barrier would degrade performance. Attaining the high volume fraction (55 wt. %) of U/Mo assumed in the computational study while maintaining the current fuel plate acceptance level at the fuel manufacturer is unlikely, i.e. no increase in the percentage of plates rejected for non-compliance with the fuel specification. Substitution of a zirconium alloy for Al would significantly increase the weight of the fuel element, the cost of the fuel element, and introduce an as-yet untried manufacturing process. A monolithic U-10Mo foil is the choice of LEU fuel for HFIR. Preliminary calculations indicate that with a modest increase in reactor power, the flux performance of the reactor can be maintained at the current level. A linearly-graded, radial fuel thickness profile is preferred to the arched profile currently used in HEU fuel because the LEU fuel media is a metal alloy foil rather than a powder. Developments in analysis capability and nuclear data processing techniques are underway with the goal of verifying the preliminary calculations of LEU flux performance. A conceptual study of the operational cost of an LEU fuel fabrication facility yielded the conclusion that the annual fuel cost to the HFIR would increase significantly from the current, HEU fuel cycle. Though manufacturing can be accomplished with existing technology, several engineering proof-of-principle tests would be required. The RERTR program is currently conducting a series of generic fuel qualification tests at the Advanced Test Reactor. A review of these tests and a review of the safety basis for the current, HEU fuel cycle led to the identification of a set of HFIR-specific fuel qualification tests. Much additional study is required to formulate a HFIR-specific fuel qualification plan from this set. However, one such test - creating a graded fuel profile across a flat foil - has been initiated with promising results.
Download or read book Low Enriched Uranium Core Design for the Massachusetts Institute of Technology Reactor MITR with Un finned 12 Mil thick Clad UMo Monolithic Fuel written by and published by . This book was released on 2013 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Performance of Low enriched U3Si2 aluminum Dispersion Fuel Elements in the Oak Ridge Research Reactor written by G. L. Copeland and published by . This book was released on 1987 with total page 130 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Neutronic Design for a Lithium cooled Reactor for Space Applications written by Charles L. Whitmarsh (Jr.) and published by . This book was released on 1971 with total page 52 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Technical Basis in Support of the Conversion of the University of Missouri Research Reactor MURR Core from Highly enriched to Low enriched Uranium steady state Thermal hydraulic Analysis written by and published by . This book was released on 2013 with total page 97 pages. Available in PDF, EPUB and Kindle. Book excerpt: The thermal performance of the proposed low-enriched uranium (LEU) core for the University of Missouri Research Reactor (MURR) during steady-state operation is predicted.
Download or read book Critical Experiments on Low enriched Uranium Oxide Systems with H U written by G. R. Goebel and published by . This book was released on 1980 with total page 60 pages. Available in PDF, EPUB and Kindle. Book excerpt:
