13 research outputs found
LIQUID LEAD-BISMUTH EUTECTIC AS A COOLANT IN GENERATION IV NUCLEAR REACTORS AND IN HIGH TEMPERATURE SOLAR CONCENTRATOR APPLICATIONS: CHARACTERISTICS, CHALLENGES, ISSUES
Heavy liquid metals have found a wide range of application in energy conversion systems, due to their beneficial thermal properties, especially their low melting points and their capability of operating at higher temperatures without boiling. In addition, the neutronic properties of various liquid metals make them attractive for fusion as well as in Generation IV nuclear reactors. Lately, concentrated solar power (CSP) systems have developed an interest in this technology, calling for temperatures up to 800 oC. The main challenge in realizing engineering scale units is to find proper structural materials that can withstand the corrosion and provide mechanical strength at operation conditions. Lead-Bismuth Eutectic (LBE) is one of the main candidate coolants for liquid metal cooled reactors and solar thermal power applications due to its physical properties such as good thermal conduction, low thermal expansion and melting point, non-violent reactivity to water and low neutron absorption. However, the key limiting factor for LBE usage is the fact of its high corrosiveness to steels and other structural materials. In this work, the results of our systematic materials study in liquid LBE and its alternatives are presented. Various potential structural materials were exposed to LBE, Roseās metal (Pb-Bi-Sn) and Pb-Bi-Zn eutectic, in static corrosion tests. Post corrosion characterization was conducted by micro-structural analysis (SEM/EDS, X-ray diffraction, Raman spectroscopy) and preferential corrosion mechanisms were evaluated.Heavy liquid metals have found a wide range of application in energy conversion systems, due to their beneficial thermal properties, especially their low melting points and their capability of operating at higher temperatures without boiling. In addition, the neutronic properties of various liquid metals make them attractive for fusion as well as in Generation IV nuclear reactors. Lately, concentrated solar power (CSP) systems have developed an interest in this technology, calling for temperatures up to 800 oC. The main challenge in realizing engineering scale units is to find proper structural materials that can withstand the corrosion and provide mechanical strength at operation conditions. Lead-Bismuth Eutectic (LBE) is one of the main candidate coolants for liquid metal cooled reactors and solar thermal power applications due to its physical properties such as good thermal conduction, low thermal expansion and melting point, non-violent reactivity to water and low neutron absorption. However, the key limiting factor for LBE usage is the fact of its high corrosiveness to steels and other structural materials. In this work, the results of our systematic materials study in liquid LBE and its alternatives are presented. Various potential structural materials were exposed to LBE, Roseās metal (Pb-Bi-Sn) and Pb-Bi-Zn eutectic, in static corrosion tests. Post corrosion characterization was conducted by micro-structural analysis (SEM/EDS, X-ray diffraction, Raman spectroscopy) and preferential corrosion mechanisms were evaluated
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Interim Status Report on Lead-Cooled Fast Reactor (Lfr) Research and Development.
This report discusses the status of Lead-Cooled Fast Reactor (LFR) research and development carried out during the first half of FY 2008 under the U.S. Department of Energy Generation IV Nuclear Energy Systems Initiative. Lead-Cooled Fast Reactor research and development has recently been transferred from Generation IV to the Reactor Campaign of the Global Nuclear Energy Partnership (GNEP). Another status report shall be issued at the end of FY 2008 covering all of the LFR activities carried out in FY 2008 for both Generation IV and GNEP. The focus of research and development in FY 2008 is an initial investigation of a concept for a LFR Advanced Recycling Reactor (ARR) Technology Pilot Plant (TPP)/demonstration test reactor (demo) incorporating features and operating conditions of the European Lead-cooled SYstem (ELSY) {approx} 600 MWe lead (Pb)-cooled LFR preconceptual design for the transmutation of waste and central station power generation, and which would enable irradiation testing of advanced fuels and structural materials. Initial scoping core concept development analyses have been carried out for a 100 MWt core composed of sixteen open-lattice 20 by 20 fuel assemblies largely similar to those of the ELSY preconceptual fuel assembly design incorporating fuel pins with mixed oxide (MOX) fuel, central control rods in each fuel assembly, and cooled with Pb coolant. For a cycle length of three years, the core is calculated to have a conversion ratio of 0.79, an average discharge burnup of 108 MWd/kg of heavy metal, and a burnup reactivity swing of about 13 dollars. With a control rod in each fuel assembly, the reactivity worth of an individual rod would need to be significantly greater than one dollar which is undesirable for postulated rod withdrawal reactivity insertion events. A peak neutron fast flux of 2.0 x 10{sup 15} (n/cm{sup 2}-s) is calculated. For comparison, the 400 MWt Fast Flux Test Facility (FFTF) achieved a peak neutron fast flux of 7.2 x 10{sup 15} (n/cm{sup 2}-s) and the initially 563 MWt PHENIX reactor attained 2.0 x 10{sup 15} (n/cm{sup 2}-s) before one of three intermediate cooling loops was shut down due to concerns about potential steam generator tube failures. The calculations do not assume a test assembly location for advanced fuels and materials irradiation in place of a fuel assembly (e.g., at the center of the core); the calculations have not examined whether it would be feasible to replace the central assembly by a test assembly location. However, having only fifteen driver assemblies implies a significant effect due to perturbations introduced by the test assembly. The peak neutron fast flux is low compared with the fast fluxes previously achieved in FFTF and PHENIX. Furthermore, the peak neutron fluence is only about half of the limiting value (4 x 10{sup 23} n/cm{sup 2}) typically used for ferritic steels. The results thus suggest that a larger power level (e.g., 400 MWt) and a larger core would be better for a TPP based upon the ELSY fuel assembly design and which can also perform irradiation testing of advanced fuels and materials. In particular, a core having a higher power level and larger dimensions would achieve a suitable average discharge burnup, peak fast flux, peak fluence, and would support the inclusion of one or more test assembly locations. Participation in the Generation IV International Forum Provisional System Steering Committee for the LFR is being maintained throughout FY 2008. Results from the analysis of samples previously exposed to flowing lead-bismuth eutectic (LBE) in the DELTA loop are summarized and a model for the oxidation/corrosion kinetics of steels in heavy liquid metal coolants was applied to systematically compare the calculated long-term (i.e., following several years of growth) oxide layer thicknesses of several steels
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Materials selection for nuclear applications: Challenges and opportunities
We discuss the challenge of selecting materials for nuclear applications and outline the need for comprehensive databases to assist scientists and engineers in choosing materials that meet interdependent physical, chemical, and nuclear criteria. In conventional engineering, chemical and physical properties and the electronic structure of materials are typically the primary considerations; nuclear applications must also consider the nuclear physics characteristics of a material. Development of databases that correlate physical, chemical, and nuclear properties would accelerate and facilitate innovations in nuclear design
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Materials selection for nuclear applications: Challenges and opportunities
We discuss the challenge of selecting materials for nuclear applications and outline the need for comprehensive databases to assist scientists and engineers in choosing materials that meet interdependent physical, chemical, and nuclear criteria. In conventional engineering, chemical and physical properties and the electronic structure of materials are typically the primary considerations; nuclear applications must also consider the nuclear physics characteristics of a material. Development of databases that correlate physical, chemical, and nuclear properties would accelerate and facilitate innovations in nuclear design
A clinical evaluation of the Zygoma fixture: One year of follow-up at 16 clinics
Purpose. To evaluate treatment outcome with Zygoma fixtures (Nobel Biocare, Goteborg, Sweden) with regard to fixture survival, patient satisfaction, and function of prosthesis replacement. Materials and Methods: The treatment outcome of 76 patients treated with 145 Zygoma fixtures at 16 centers was evaluated. Patient's and dentist's evaluations of the functional and aesthetic outcome of the treatment were assessed at delivery of prosthesis and at the 1-year follow-up visit. At the 1-year follow-up visit, the status of the peri-implant mucosa around the abutments and the amount of plaque were registered. Results: Sixty-six of the 76 patients, with 124 Zygoma fixtures supporting the prosthetic restorations, were evaluated at the 1-year follow-up. The overall survival rate for the Zygoma fixtures was 97.9% after 1-year of follow-up. Eighty percent of the patients were fully satisfied with both aesthetic and functional outcome at the time of prosthetic insertion and at the 1-year follow-up. All reported data from the dentists, with the exception of one restoration with several abutment screw loosenings, scored from acceptable to excellent for the aesthetic and functional outcome of the treatment. The status of peri-implant mucosa was recorded as normal in approximately 60% of the sites. Plaque, when present, was more often detected on the palatal surfaces compared with the buccal surfaces. Conclusion: This 1-year follow-up of Zygoma fixtures has shown good results with an acceptable number of minor complications and a majority of satisfied patients. (C) 2004 American Association of Oral and Maxillofacial Surgeons
Clinical evaluation of the zygoma implant: 3-year follow-up at 16 clinics
Purpose: The purpose of this clinical investigation was to evaluate the treatment outcome with zygoma implants with regard to implant survival, patient satisfaction, and function of prosthesis replacement after 3 years. Patients and Methods: The treatment outcome of 76 patients treated with 145 zygoma fixtures at 16 centers was evaluated with regard to implant survival. Status of peri-implant mucosa and amount of plaque were registered annually. Patients' and dentists' evaluations of the functional and esthetic outcome of the treatment were assessed at delivery of prosthesis and thereafter at each follow-up visit. Results: Sixty of 76 patients were followed for 3 years after prosthetic delivery. Five of 145 placed zygoma implants failed during the course of the study resulting in an overall implant survival rate of 96.3%. At the 3-year follow-up, 75% of the implants sites were registered with normal peri-implant mucosa and 68% with no visible plaque. The patients were fully satisfied with the esthetic and functional outcome of the treatment in 86% and 71%, respectively, at the 3-year follow-up visit. All reported data from dentists scored from acceptable to excellent. Conclusion: The multicenter study showed a high predictability of the zygoma implant-supported rehabilitation. (c) 2007 American Association of Oral and Maxillofacial Surgeons