2 edition of Improved Performance For uo2 Fuel. found in the catalog.
Improved Performance For uo2 Fuel.
Atomic Energy of Canada Limited.
Published
1973
by s.n in S.l
.
Written in
Edition Notes
1
| Series | Atomic Energy of Canada Limited. AECL -- 4366 |
| Contributions | Robertson, J.A.L. |
| ID Numbers | |
|---|---|
| Open Library | OL21971337M |
By understanding the underlying mechanisms that govern fuel properties fuel performance codes can be improved and new fuels can be developed. Additives have been added to UO2 during sintering to increase grain size with the aim of reducing fission gas release and increasing pellet plasticity.}. Nishida, T. and Yuda, R. () Effect of Particle Size and Oxygen Potential on UO2-Gd2O3 Pellet Sintering, Advances in Fuel Pellet Technology for Improved Performance at High Burnup. Proceedings of Technical Committee Meeting, IAEA TECH DOC, ,
@article{osti_, title = {Effect of point defects on the thermal conductivity of UO2: molecular dynamics simulations}, author = {Liu, Xiang-Yang and Stanek, Christopher Richard and Andersson, Anders David Ragnar}, abstractNote = {The thermal conductivity of uranium dioxide (UO2) fuel is an important materials property that affects fuel performance since it is a key . In order to develop a novel proton exchange membrane fuel cell (PEMFC), new materials were investigated in order to increase the water uptake of the membrane known commercially as “Nafion” by casting it with zirconium metal organic frameworks (MOFs) (i.e., MOF and ) to form a composite using sol-gel method. It was found that the water uptake of .
UO 2-BeO is one of the most promising accident tolerant nuclear fuels due to its excellent thermal conductivity compared to pure UO 2 fuel. Two different UO 2-BeO fabrication methods have demonstrated the capability to fabricate enhanced thermal conductivity UO 2-BeO composite fuels and improve fuel one method, BeO is continuously distributed around UO 2 . Abstract. The University of Florida (UF) evaluated a composite fuel consisting of UO 2 powder mixed with diamond micro particles as a candidate as an accident-tolerant fuel (ATF). The research group had previous extensive experience researching with diamond micro particles as an addition to reactor coolant for improved plant thermal performance.
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NUCLEAR ENGINEERING AND DESIGN 21 () NORTH-HOLLAND PUBLISHING COMPANY UO2 PROPERTIES AFFECTING PERFORMANCE* M.F. LYONS, R.F. BOYLE, J.H. DAVIES, V.E. HAZEL, and T.C. ROWLAND Nuclear Fuel Department, General Electric Company, San Jose, CaliforniaU.S.A.
Received 24 June UO2 has become the basic reference fuel Cited by: In any practical application, this penalty must be weighed against the improved I.J Htmgs, R.D MacDonald / High hurnup performance of annular UO^ fuel fission gas release characteristics of disc fuel coupled with the lower sheath strain and Improved Performance For uo2 Fuel.
book elongation ob- tained with a pellet l/d of [5,9]. Conclusions by: 4. Comparison of fuel/clad interaction products on (a) and (c) intragranular fission gas precipitation at pellet bore MgO doped fuel and (b) reference (UO;) fuel (X ).
(all x ). Sawbridge al. I Irradiation performance of VOi fuel Sections were taken at similar positions m each pin although there was little axial variation in by: Uranium dioxide is a ceramic refractory uranium compound, in many cases used as a nuclear fuel.
Most of LWRs use the uranium fuel, which is in the form of uranium dioxide (chemically UO 2).Uranium dioxide is a black semiconducting solid with very low thermal conductivity. International Journal of Nuclear Energy Science and Engineering (IJNESE) Volume 5, doi: /ijnese Thermal Performance of UO2‐BeO Fuel during a Loss of.
Nuclear Engineering and Design 56 () North-Holland Publishing Company PECITIS-II, A COMPUTER PROGRAM TO PREDICT THE PERFORMANCE OF COLLAPSIBLE CLAD UO2 FUEL ELEMENTS * A.K. ANAND, K. ANANTHARAMAN and V. SARDA Reactor Engineering Division, Bhabha Atomic Research Centre, Trombay, BombayIndia Received 17 March The codes devised and used in India for the design of fuel.
Variable dependence and concluding remarks. The melting temperature of the fuel is a function of the fuel composition (PuO 2 and UO 2 fractions), O/M ratio or deviation from stoichiometry, and burnup. The melting temperature decreases with increasing PuO 2 content, with increasing burnup, and with deviations from stoichiometry.
The MOX fuel will melt at a lower temperature than UO 2 fuel. It also reviews the experimental evidence for improved gas retention in large grain UO2. Finally the choices for possible large-scale development are discussed. Pin dimensional changes.
Changing the grain size of UO2 fuel might also be expected to change other, particularly the mechanical, properties of the fuel. This may, in turn. Marsh, G.A.
Wood, C.P. Perkins, Niobia-doped UO2 Fuel Manufacturing Experience at BNFL, Technical Committee Meeting on Advances in Fuel Pellet Technology for Improved Performance at High Burnup. UO2-BeO composite fuel may enable Light Water Reactors (LWRs) to have better safety due to its higher thermal conductivity.
Much work have been done on the analysis of UO2-BeO fuel performance during LWRs steady state and Loss of Coolant Accident (LOCA) conditions using hypothetical thermal properties and behaviors models, leading to much. It forms the cornerstone of BNFL's New Oxide Fuel Complex, due on stream in ‐ This paper summarizes key points arising from the 20‐year history of the process: the consistency and reliability of the product, its performance from a fuel fabricator's viewpoint, and developments made to improve the process since its introduction.
To better interpret the experimental results and improve the capability of the fuel performance codes to predict high burnup fuel behavior, this thesis developed mechanistic models of. Based on the high-burnup fuel data available in open literature, a conservative width of high-burnup structure (HBS) in light water reactor UO2 fuel, which can be used for fuel performance.
Fuel swelling being very slow, might be less damageable. Such difficulties can be only partially overcome by improved operating procedures, and a residual rate of failure is hardly avoidable. Moreover, tubing of higher initial ductility does not necessarily provide better fuel performance, since a significant residual ductility is not ensured.
A Computer Program to Predict the Performance of UO2 Fuel Elements Irradiated at High Power Outputs to a Burnup of 10 MWd/MTu. Nuclear Applications and Technology: Vol. 9, No. 2, pp. (). Accident-Tolerant-Fuel Performance Analysis of APMT Steel Clad/UO2 Fuel and APMT Steel Clad/UN-U3Si5 Fuel Concepts.
Nuclear Science and Engineering: Vol. No. 4, pp. The fission gas release microscopic model of the mechanistic code MFPR is further developed for modelling of enhanced release from irradiated UO2 fuel. Books. A-Z of books and conference proceedings 85 90© The British Nuclear Energy Society unless otherwise stated Introduction Zircaloy-4 Cladding Performance UO2 Fuel Performance Fuel — Cladding Interaction Conclusions Acknowledgements Zircaloy-4 cladding UO- test rods were irradiated in the Zorita reactor and achieved burnups up to.
A densifcation algorithm for irradiated UO2 fuel, modified to reflect a rapid densification rate from 0 to 10 MW.h/kg U, is presented. Included in a fuel performance code, the algorithm gives improve. Request PDF | Manufacture of a UO2-Based Nuclear Fuel with Improved Thermal Conductivity with the Addition of BeO | The low thermal conductivity of oxide nuclear fuels is a performance.
The relatively poor thermal conductivity of the UO2 fuel is a major challenge for optimizing reactor operation and safety performance, despite its widespread use in the majority of power reactors.The CERMET samples consist of depleted uranium dioxide (UO2) fuel particles in a tungsten metal matrix, which has been demonstrated on previous programs to provide improved performance and retention of fission products1.
Numerous past programs have utilized hot hydrogen furnace testing to develop and evaluate fuel [email protected]{osti_, title = {The effect of fuel chemistry on UO2 dissolution}, author = {Casella, Amanda and Hanson, Brady and Miller, William}, abstractNote = {The dissolution rate of both unirradiated UO2 and used nuclear fuel has been studied by numerous countries as part of the performance assessment of proposed geologic repositories.
