45 research outputs found
ILAS LAGLOBAL Seminar Series: Talking about Objects of Knowledge
No full textInstitute of Latin American Studies : 4 November 2020, 5.30pm - 7.30pm : Seminar Online : Professor Helen Cowie (University of York), author of Conquering Nature in Spain and Its Empire, 1750–1850 (Manchester, 2011) and Exhibiting Animals in Nineteenth-Century Britain, (Palgrave, 2014). Convenor: Professor Mark Thurner (ILAS) ILAS LAGLOBAL AUTUMN 2020 WEBINAR SERIES.pdf Read more HER
ILAS LAGLOBAL Seminar Series: Talking about Objects of Knowledge
No full textInstitute of Latin American Studies : 21 October 2020 17h30-19h30 : Seminar Online : Professor Jorge Cañizares-Esguerra (University of Texas at Austin), author of How to Write the History of the New World, (Stanford, 2001) and Nature, Empire and Nation (Stanford, 2006). Convenor : Professor Mark Thurner (ILAS) ILAS LAGLOBAL AUTUMN 2020 WEBINAR SERIES.pdf See more HER
Foreword: Special Issue on the International Topical Meeting on Reactor Physics PHYSOR 2012
No full text
ILAS LAGLOBAL Seminar Series: Talking about Objects of Knowledge
No full textLondon : 7 October 2020 17h30-19h30 : Seminar - Venue Online : Professor Miruna Achim (Universidad Autonoma Metropolitana, Mexico City), author of From Idols to Antiquity : Forging the National Museum of Mexico (Nebraska, 2017). Convenor : Professor Mark Thurner (ILAS) Read more : https://ilas.sas.ac.uk/events/event/2281
Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation - Vandellos II Reactor
No full textThis report is one of the several recent NUREG/CR reports documenting benchmark-quality radiochemical assay data and the use of the data to validate computer code predictions of isotopic composition for spent nuclear fuel, to establish the uncertainty and bias associated with code predictions. The experimental data analyzed in the current report were acquired from a high-burnup fuel program coordinated by Spanish organizations. The measurements included extensive actinide and fission product data of importance to spent fuel safety applications, including burnup credit, decay heat, and radiation source terms. Six unique spent fuel samples from three uranium oxide fuel rods were analyzed. The fuel rods had a 4.5 wt % {sup 235}U initial enrichment and were irradiated in the Vandellos II pressurized water reactor operated in Spain. The burnups of the fuel samples range from 42 to 78 GWd/MTU. The measurements were used to validate the two-dimensional depletion sequence TRITON in the SCALE computer code system
Low-Enriched Uranium Fuel Design with Two-Dimensional Grading for the High Flux Isotope Reactor
No full textAn 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
Recommended from our members
Fuel Grading Study on a Low-Enriched Uranium Fuel Design for the High Flux Isotope Reactor
No full textAn engineering design study that would enable the conversion of the High Flux Isotope Reactor (HFIR) from high-enriched uranium to low-enriched uranium fuel is ongoing at Oak Ridge National Laboratory. The computational models used to search for a low-enriched uranium (LEU) fuel design that would meet the requirements for the conversion study, and the recent results obtained with these models during FY 2009, 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 high-enriched uranium fuel core. These studies 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
