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Author : Sylvie Marie Aurel̓ie Reynaud
Publisher :
ISBN 13 :
Total Pages : 152 pages
Book Rating : 4.:/5 (515 download)
Download or read book Nitride Fuel Performance written by Sylvie Marie Aurel̓ie Reynaud and published by . This book was released on 2002 with total page 152 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 15 pages
Book Rating : 4.:/5 (685 download)
Download or read book Irradiation Performance of Nitride Fuels written by and published by . This book was released on 1993 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: The properties and advantages of nitride fuels are well documented in the literature. Basically the high thermal conductivity and uranium density of nitride fuels permit high power density, good breeding ratios, low reactivity swings, and large diameter pins compared to oxides. Nitrides are compatible with cladding alloys and liquid metal coolants, thereby reducing fuel/cladding chemical interactions and permitting the use of sodium-bonded pins and the operation of breached pins. Recent analyses done under similar operating conditions show that - compared to metal - fuels mixed nitrides operate at lower temperatures, produce less cladding strain, have greater margins to failure, result in lower transient temperatures, and have lower sodium void reactivity. Uranium nitride fuel pellet fabrication processes were demonstrated during the SP-100 program, and irradiated nitride fuels can be reprocessed by the PUREX process. Irradiation performance data suggest that nitrides have low fission gas release and swelling rates thereby permitting favorable pin designs and long lifetime. The objective of this report is to summarize the available nitride irradiation performance data base and to recommend optimum nitride characteristics for use in advanced liquid metal reactors.
Download or read book Predicting Nitride Fuel Performance for SP-100 Conditions written by and published by . This book was released on 1986 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper reports on the methods used to evaluate the performance of the nitride fuel design proposed for the SP-100 thermoelectric concept.
Author : J. Ahn
Publisher :
ISBN 13 :
Total Pages : 91 pages
Book Rating : 4.:/5 (316 download)
Download or read book Laboratory Directed Research and Development (LDRD) on Mono-uranium Nitride Fuel Development for SSTAR and Space Applications written by J. Ahn and published by . This book was released on 2006 with total page 91 pages. Available in PDF, EPUB and Kindle. Book excerpt: The US National Energy Policy of 2001 advocated the development of advanced fuel and fuel cycle technologies that are cleaner, more efficient, less waste-intensive, and more proliferation resistant. The need for advanced fuel development is emphasized in on-going DOE-supported programs, e.g., Global Nuclear Energy Initiative (GNEI), Advanced Fuel Cycle Initiative (AFCI), and GEN-IV Technology Development. The Directorates of Energy & Environment (E & amp;E) and Chemistry & Material Sciences (C & amp;MS) at Lawrence Livermore National Laboratory (LLNL) are interested in advanced fuel research and manufacturing using its multi-disciplinary capability and facilities to support a design concept of a small, secure, transportable, and autonomous reactor (SSTAR). The E & E and C & MS Directorates co-sponsored this Laboratory Directed Research & Development (LDRD) Project on Mono-Uranium Nitride Fuel Development for SSTAR and Space Applications. In fact, three out of the six GEN-IV reactor concepts consider using the nitride-based fuel, as shown in Table 1. SSTAR is a liquid-metal cooled, fast reactor. It uses nitride fuel in a sealed reactor vessel that could be shipped to the user and returned to the supplier having never been opened in its long operating lifetime. This sealed reactor concept envisions no fuel refueling nor on-site storage of spent fuel, and as a result, can greatly enhance proliferation resistance. However, the requirement for a sealed, long-life core imposes great challenges to research and development of the nitride fuel and its cladding. Cladding is an important interface between the fuel and coolant and a barrier to prevent fission gas release during normal and accidental conditions. In fabricating the nitride fuel rods and assemblies, the cladding material should be selected based on its the coolant-side corrosion properties, the chemical/physical interaction with the nitride fuel, as well as their thermal and neutronic properties. The US NASA space reactor, the SP-100 was designed to use mono-uranium nitride fuel. Although the SP-100 reactor was not commissioned, tens of thousand of nitride fuel pellets were manufactured and lots of them, cladded in Nb-1-Zr had been irradiated in fast test reactors (FFTF and EBR-II) with good irradiation results. The Russian Naval submarines also use nitride fuel with stainless steel cladding (HT-9) in Pb-Bi coolant. Although the operating experience of the Russian submarine is not readily available, such combination of fuel, cladding and coolant has been proposed for a commercial-size liquid-metal cooled fast reactor (BREST-300). Uranium mono-nitride fuel is studied in this LDRD Project due to its favorable properties such as its high actinide density and high thermal conductivity. The thermal conductivity of mono-nitride is 10 times higher than that of oxide (23 W/m-K for UN vs. 2.3 W/m-K for UO{sub 2} at 1000 K) and its melting temperature is much higher than that of metal fuel (2630 C for UN vs. 1132 C for U metal). It also has relatively high actinide density, (13.51 gU/cm{sup 3} in UN vs. 9.66 gU/cm{sup 3} in UO{sub 2}) which is essential for a compact reactor core design. The objective of this LDRD Project is to: (1) Establish a manufacturing capability for uranium-based ceramic nuclear fuel, (2) Develop a computational capability to analyze nuclear fuel performance, (3) Develop a modified UN-based fuel that can support a compact long-life reactor core, and (4) Collaborate with the Nuclear Engineering Department of UC Berkeley on nitride fuel reprocessing and disposal in a geologic repository.
Author :
Publisher :
ISBN 13 :
Total Pages : 8 pages
Book Rating : 4.:/5 (727 download)
Download or read book Performance Analysis of a Mixed Nitride Fuel System for an Advanced Liquid Metal Reactor written by and published by . This book was released on 1990 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: The conceptual development and analysis of a proposed mixed nitride driver and blanket fuel system for a prototypic advanced liquid metal reactor design has been performed. As a first step, an intensive literature survey was completed on the development and testing of nitride fuel systems. Based on the results of this survey, prototypic mixed nitride fuel and blanket pins were designed and analyzed using the SIEX computer code. The analysis predicted that the nitride fuel consistently operated at peak temperatures and cladding strain levels that compared quite favorably with competing fuel designs. These results, along with data available in the literature on nitride fuel performance, indicate that a nitride fuel system should offer enhanced capabilities for advanced liquid metal reactors. 13 refs., 10 figs., 2 tabs.
Author : Richard Moore
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (316 download)
Download or read book Nitride Fuel Modeling Recommendation for Nitride Fuel Material Property Measurement Priority written by Richard Moore and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The purpose of this effort was to provide the basis for a model that effectively predicts nitride fuel behavior. Material property models developed for the uranium nitride fuel system have been used to approximate the general behavior of nitride fuels with specific property models for the transuranic nitride fuels utilized as they become available. The AFCI fuel development program now has the means for predicting the behavior of the transuranic nitride fuel compositions. The key data and models needed for input into this model include:Thermal conductivity with burnupFuel expansion coefficientFuel swelling with burnupFission gas release with burnup. Although the fuel performance model is a fully functional FEA analysis tool, it is limited by the input data and models.
Author : Yu. M. Golovchenko
Publisher :
ISBN 13 :
Total Pages : 15 pages
Book Rating : 4.:/5 (812 download)
Download or read book Study on the Performance of Fuel Elements with Carbide and Carbide-nitride Fuels written by Yu. M. Golovchenko and published by . This book was released on 1988 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Frank Joseph Szakaly
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (711 download)
Download or read book Assessment of Uranium-free Nitride Fuels for Spent Fuel Transmutation in Fast Reactor Systems written by Frank Joseph Szakaly and published by . This book was released on 2004 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The purpose of this work is to investigate the implementation of nitride fuels containing little or no uranium in a fast-spectrum nuclear reactor to reduce the amount of plutonium and minor actinides in spent nuclear fuel destined for the Yucca Mountain Repository. A two tier recycling strategy is proposed. Thermal spectrum transmutation systems converted from the existing LWR fleet were modeled for the first tier, and the Japanese fast reactor MONJU was used for the fast-spectrum transmutation. The modeling was performed with the Monteburns code. Transmutation performance was investigated as well as delayed neutron fraction, heat generation rates, and radioactivity of the spent material in the short and long term for the different transmutation fuel cycles. A two-tier recycling strategy incorporating fast and thermal transmutation with uranium-free nitride fuel was shown to reduce the long-term heat generation rates and radioactivity of the spent nuclear fuel inventory.
Download or read book Performance Potential of (Th, U) Carbide and (Th, U) Nitride Fuel in 1200 MWe LMFBR's written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: An evaluation of the performance potential of thorium-uranium carbide and nitride fuel in 1200 MW(e) homogeneous and heterogeneous LMFBR's has been completed. Comparisons were done with 9.40 mm outer diameter, 0.38 mm cladding fuel pins at a selected peak (3 sigma) linear power of 98.4 kW/m for all cores. Breeding ratios for the homogeneous (Th, U)C and (Th, U)N cores are 1.12 and 1.16, respectively. In the heterogeneous cores the breeding ratios are 0.08 to 0.09 greater. A comparative breeding ratio of 1.48 results for a sodium-bonded (U, Pu)C homogeneous LMFBR with similar design criteria. Compound inventory doubling times for the homogeneous and heterogeneous (Th, U)C cores are 82 and 53 years, respectively. Additional performance parameters have also been compared, including sodium void worths, specific inventories, fissile material gains, and equilibrium cycle reactivity losses.
Download or read book Breeding Performance of Carbide and Nitride Fuels in 2000 MWe LMFBRs written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The assumptions, constraints, and methodology used in the design and analysis of 2000 MWe LMFBRs using carbide and nitride fuel are presented. The assumptions used in the nuclear, thermal and mechanical designs are discussed together with geometry constraints, operational constraints, performance constraints, constraints coming from fabrication consideration and fuel bundle-duct interaction constraints. The basic calculational flow for system design studies is described, and the computer codes used in the analyses are briefly reviewed.
Author : Guillaume Giudicelli
Publisher :
ISBN 13 :
Total Pages : 124 pages
Book Rating : 4.:/5 (11 download)
Download or read book Achievable Power Uprates in Pressurized Water Reactors Using Uranium Nitride Fuel written by Guillaume Giudicelli and published by . This book was released on 2017 with total page 124 pages. Available in PDF, EPUB and Kindle. Book excerpt: This work aims at investigating the potential benefits of nitride fuel use in pressurized water reactors. The AP1000 is chosen as the reference power plant. Both oxide and nitride fuel are considered and compared using a steady state thermal hydraulics and mechanics parametric optimization study to achieve a maximal core power. A subsequent neutronics study determined the achievable energy extracted per fuel mass (burnup) and sets the core power that allows for an 18-months fuel cycle length. The impact of the change in the core operating temperature on the steam cycle efficiency is considered in order to provide a final evaluation of the electric power uprate. The steady state limits considered are pressure drop, minimum departure from nucleate boiling ratio, fretting and sliding wear and fuel average and centerline temperatures. These limits were set by the reference design's performance. Two strategies were used to raise the core power while remaining within specified limits: increasing the core mass flow rate and decreasing the core inlet temperature. These two strategies were implemented in a simplified MATLAB tool using correlations and a MATLAB-VIPRE (subchannel simulation tool) interface to better model cross-flows. Designs with smaller pins but with similar pitch-todiameter ratios compared to the reference design were found to be optimal with regards to these performances for both strategies. Fretting wear was found to be the limiting constraint for these designs for the first strategy, and additional spacer grids can be introduced to reduce fretting wear and to allow a further power increase. MDNBR was found to be the limiting constraint for these designs in the second strategy. The fuel temperature was not limiting for these designs and both oxide and nitride fuel can be utilized with the same uprates. Both tools provided similar results: smaller fuel pins with similar pitch over diameter ratios allow for better performances than the nominal design in the aforementioned criteria. The most promising strategy proved to be decreasing the core inlet temperature. With this strategy, the possible uprate is 16%, or 550 MWth, in both tools. Such an uprate requires an additional steam generator, and when lowering the core inlet temperature the efficiency of the steam cycle is lowered by 1% as we also need to lower the steam generator saturation pressure. This will require a larger high-pressure turbine. The optimized nitride-fueled design was compared with the oxide-fueled nominal core in terms of neutronics performances. I showed that the new design can reach an 18 month cycle length, at an uprated power, with a 4.3% enrichment and a 60 assembly feed using uranium nitride, compared with a 4.6% enrichment and a 68 assembly feed for the nominal design at the nominal power. With a higher enrichment and a higher feed, a two-year cycle length can be reached even with the uprate. The moderator temperature coefficient, the shutdown margin and the power coefficient of both designs satisfied licensing requirements. A 5% increase in fuel cycle costs was noted with the nitride optimized core, minor compared to the revenue of a 150 MWe uprate. Transient performances, and more extensive fuel performance studies are left for future studies.
Download or read book Advancing Liquid Metal Reactor Technology with Nitride Fuels written by and published by . This book was released on 1991 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A review of the use of nitride fuels in liquid metal fast reactors is presented. Past studies indicate that both uranium nitride and uranium/plutonium nitride possess characteristics that may offer enhanced performance, particularly in the area of passive safety. To further quantify these effects, the analysis of a mixed-nitride fuel system utilizing the geometry and power level of the US Advanced Liquid Metal Reactor as a reference is described. 18 refs., 2 figs., 2 tabs.
Author : Bo Feng (Ph. D.)
Publisher :
ISBN 13 :
Total Pages : 269 pages
Book Rating : 4.:/5 (823 download)
Download or read book Feasibility of Breeding in Hard Spectrum Boiling Water Reactors with Oxide and Nitride Fuels written by Bo Feng (Ph. D.) and published by . This book was released on 2011 with total page 269 pages. Available in PDF, EPUB and Kindle. Book excerpt: This study assesses the neutronic, thermal-hydraulic, and fuel performance aspects of using nitride fuel in place of oxides in Pu-based high conversion light water reactor designs. Using the higher density nitride fuel hardens the neutron energy spectrum and results in higher breeding ratios. The state-of-the-art high conversion light water reactor, the Resource-renewable Boiling Water Reactor (RBWR), served as the template core upon which comparative studies between nitride and oxide fuels were performed. A 1/3 core reactor physics model was developed for the RBWR using the stochastic transport code MCNP. The code was coupled with a lumped channel thermalhydraulics 5-channel model for steady-state analyses. The depletion code MCODE, which links MCNP with ORIGEN, was used for all burnup calculations. Select physics parameters were calculated and with the exception of the void coefficients, agreed with reported data. The void coefficients of the coupled core were calculated to be slightly positive using two different methods (10% power increase and 5% flow reduction). The standard RBWR assembly designs, which use tight lattice hexagonal fuel rod arrays, with oxide fuel were then replaced with various nitride fuel assembly designs to determine the potential increase in breeding ratio, the potential to breed with pressurized water, and the potential to improve the critical power ratio with a wider pin pitch. Without changing the assembly geometry or discharge burnup, using nitride fuel resulted in a breeding ratio of 1.14. Using single-phase liquid water, the nitride fuel RBWR assembly resulted in a conversion ratio of 1.00. Another nitride fuel assembly design with boiling water maintained a 1.04 breeding ratio while increasing the pitch-todiameter ratio from 1.13 to 1.20. This modification increased the hot assembly critical power ratio from 1.22 to 1.36, as calculated using the Liu-2007 correlation. A high-porosity nitride fuel is recommended for high burnup conditions, to accommodate the nitride fuel's higher swelling and less favorable mechanical properties compared to the oxide fuel. The high porosity allows additional volume for pressure-induced densification, alleviating swelling and subsequent cladding strain. To predict the performance of high-porosity nitride fuel, fission gas and fuel behavior mechanistic models were developed for high burnup and low-temperature conditions. These models were validated with reported irradiation data and implemented, along with fuel material properties, into the steady-state fuel behavior code FRAPCON-EP. Under simulated RBWR conditions, a fuel density no more than 85% of theoretical density is recommended to maintain satisfactory fuel performance.
Author :
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ISBN 13 :
Total Pages : 720 pages
Book Rating : 4.E/5 ( download)
Download or read book TID. written by and published by . This book was released on 19?? with total page 720 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Breeding Performance of Carbide and Nitride Fuels in 2000 MWe LMFBRs. Part IV written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Impact on pin diameter optimization and breeding performance from either a constant coolant velocity (25 ft/sec) constraint or a constant fuel bundle pressure drop (40 psi) constraint has been evaluated, and comparisons of these results are given. The 40 psi fuel bundle pressure drop was chosen not to imply a limit of pump technology, but because it corresponds to acceptable coolant velocities in the range of 25 ft/sec ro 35 ft/sec for various pin diameters and linear heat ratings.
Author : U.S. Atomic Energy Commission. Division of Plans and Reports
Publisher :
ISBN 13 :
Total Pages : 768 pages
Book Rating : 4.3/5 (91 download)
Download or read book Atomic Energy Research written by U.S. Atomic Energy Commission. Division of Plans and Reports and published by . This book was released on 1970 with total page 768 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : U.S. Atomic Energy Commission. Division of Plans and Reports
Publisher :
ISBN 13 :
Total Pages : 344 pages
Book Rating : 4.3/5 (91 download)
Download or read book Fundamental Nuclear Energy Research written by U.S. Atomic Energy Commission. Division of Plans and Reports and published by . This book was released on 1969 with total page 344 pages. Available in PDF, EPUB and Kindle. Book excerpt:
