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Expert system applications in support of system diagnostics and prognostics at EBR-II

Description: Expert systems have been developed to aid in the monitoring and diagnostics of the Experimental Breeder Reactor-II (EBR-II) at the Idaho National Engineering Laboratory (INEL) in Idaho Falls, Idaho. Systems have been developed for failed fuel surveillance and diagnostics and reactor coolant pump monitoring and diagnostics. A third project is being done jointly by ANL-W and EG G Idaho to develop a transient analysis system to enhance overall plant diagnostic and prognostic capability. The failed fuel surveillance and diagnosis system monitors, processes, and interprets information from nine key plant sensors. It displays to the reactor operator diagnostic information needed to make proper decisions regarding technical specification conformance during reactor operation with failed fuel. 8 refs., 9 figs., 2 tabs.
Date: January 1, 1989
Creator: Lehto, W.K.; Gross, K.C. (Argonne National Lab., Idaho Falls, ID (USA) & Argonne National Lab., IL (USA))
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Partner: UNT Libraries Government Documents Department
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Kinetics of Treat Used as a Test Reactor

Description: An analysis is presented concerning the reactor kinetics of TREAT used as a pulsed, engineering test reactor for fast reactor fuel element studies. A description of the reactor performance is given for a wide range of conditions associated with its use as a test reactor. Supplemental information on meltdown experimentation is included. (J.R.D.)
Date: May 1962
Creator: Dickerman, C. E.; Johnson, R. D. & Gasidlo, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Neutron irradiation and compatibility testing of Li/sub 2/O

Description: A study was made of the neutron-irradiation behavior of /sup 6/Li-enriched Li/sub 2/O material in EBR-II. In addition, a stress-corrosion study was performed ex-reactor to test compatibility of Li/sub 2/O materials with a variety of stainless steels. Results of the irradiation testing showed that tritium and helium retention in the Li/sub 2/O (approx. 89% dense) lessened with neutron exposure. Helium and tritium retention appear to approach steady-state after approx. 1% /sup 6/Li burnup. The stress-corrosion studies, using 316 stainless steel (Ti-modified) and a 35% Ni alloy, showed that stress does not enhance the corrosion, and that dry Li/sub 2/O is not significantly corrosive, the LiOH content producing the corrosive effects. Corrosion, in general, was not severe as a passivation in sealed capsules seemed to occur after a time, greatly reducing corrosion rates.
Date: January 1, 1983
Creator: Porter, D. L.; Krsul, J. R.; Laug, M. T.; Walters, L. C. & Tetenbaum, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Design and operating experience of EBR-II intermediate heat exchanger

Description: Experimental Breeder Reactor II (EBR-II) has operated for over 15 years at the Idaho National Engineering Laboratory near Idaho Falls. EBR-II has served the nation in providing information on fuels, materials, and components under conditions approaching those expected for commercial power plants. In addition, EBR-II is a power plant generating electricity with an availability of about 70%. A key component, the Intermediate Heat Exchanger (IHX), of any Liquid Metal Fast Breeder Reactor (LMFBR) must perform with a high degree of reliability for successful commercialization. The design and operating experience gained from EBR-II demonstrates that the IHX can be built and operated with confidence that its performance and reliability will be satisfactory.
Date: December 1979
Creator: Buschman, H. W.; Koenig, J. F. & Stone, C. C.
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Partner: UNT Libraries Government Documents Department
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Off-normal performance of EBR-II (Experimental Breeder Reactor) driver fuel

Description: The off-normal performance of EBR-II Mark-II driver fuel has been more than satisfactory as demonstrated by robust reliability under repeated transient overpower and undercooled loss-of-flow tests, by benign run-beyond-cladding-breach behavior, and by forgiving response to fabrication defects including lack of bond. Test results have verified that the metallic driver fuel is very tolerant of off-normal events. This behavior has allowed EBR-II to operate in a combined steady-state and transient mode to provide test capability without limitation from the metallic driver fuel.
Date: September 1, 1986
Creator: Seidel, B.R.; Batte, G.L.; Lahm, C.E.; Fryer, R.M.; Koenig, J.F. & Hofman, G.L.
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Partner: UNT Libraries Government Documents Department
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Experience with EBR-II (Experimental Breeder Reactor) driver fuel

Description: The exceptional performance of Experimental Breeder Reactor-II (EBR-II) metallic driver fuel has been demonstrated by the irradiation of a large number of elements under steady-state, transient overpower, and loss-of-flow conditions. High burnup with high reliability has been achieved by a close coupling of element design and materials selection. Quantification of reliability has allowed full utilization of element lifetime. Improved design and duct materials currently under test are expected to increase the burnup from 8 to 14 at.%.
Date: January 1, 1986
Creator: Seidel, B. R.; Porter, D. L.; Walters, L. C. & Hofman, G. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Safety and operating experience at EBR-II: lessons for the future

Description: EBR-II is a small LMFBR power plant that has performed safely and reliably for 16 years. Much has been learned from operating it to facilitate the design, licensing, and operation of large commercial LMFBR power plants in the US. EBR-II has been found relatively easy to keep in conformity with evolving safety requirements, largely because of inherent safety features of the plant. Such features reduce dependence on active safety systems to protect against accidents. EBR-II has experienced a number of plant-transient incidents, some planned, others inadvertent; none has resulted in any significant plant damage. The operating experience with EBR-II has led to the formulation of an Operational Reliability Test Program (ORTP), aimed at showing inherently safe performance of fuel and plant systems.
Date: January 1, 1981
Creator: Sackett, J. I. & Golden, G. H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Transient performance of EBR-II driver fuel

Description: The first phases of qualification of the EBR-II driver fuel for repeated transient overpower operation have recently been completed. The accomplishments include prediction of the transient fuel and cladding performance through ex-core testing and fuel-element modeling studies, localized in-core power testing during steady-state operation, and whole-core multiple transient testing. The metallic driver fuel successfully survived 56 transients, spaced over a 45-day period, with power increases of approx. 160% at rates of approx. 1%/s with a 720-second hold at full power. The performance results obtained from both ex-core and n-core tests indicate that the fuel is capable of repeated transient operation.
Date: 1981~
Creator: Buzzell, J. A.; Hudman, G. D. & Porter, D. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Computer programs for describing the dynamic behavior of EBR-II

Description: Kinetic studies are performed at EBR-II to ensure that the dynamic characteristics of the reactor indicate integrity of the system and surrounding environment. These studies are done by analysis of power perturbations caused by a drop rod and a rod oscillator. The power perturbation following a rod drop is first analyzed by inverse-kinetics procedures to obtain a time-dependent reactivity. This reactivity is further fitted to a feedback transfer fanction characteristic of linear differential equations. The power perturbation caused by the oscillator is Fourier-analyzed to obtain a series of Fourier coefficients representing the reactor transfer function directly. The feedback transfer function is then obtained from this and the zero-power transfer function. 11 references. (auth)
Date: September 1973
Creator: Larson, H. A.; Engen, I. A.; Tuck, M. R. & Hyndman, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of ex-reactor loading event on high-fluence EBR-II control-rod thimble 5E3

Description: A Type 304 stainless steel EBR-II control-rod thimble (CRT 5E3) with high fluence was damaged while undergoing dimensional evaluation. The damage, which occurred when the thimble was inadvertently loaded in a bending mode, consisted of rather localized but extensive fracture. An elastic stress analysis of the bending mode was done on the thimble, using semimembrane shell theory. The analysis disclosed several important aspects that the simpler and more commonly employed techniques do not disclose. The hoop stress was found to be the most probable to initiate failure in that crack initiation would most likely result from localized yielding from the hoop stress. Structural assessment of the failure with the aid of scanning electron, transmission electron, and optical microscopy qualitatively supported the stress analysis in that the failure was associated with localized yielding and was accompanied by some, but limited, ductility. There was no evidence that a premature failure occurred (e.g., a failure at stresses below the yield stress of the material and which might be associated with grain-boundary embrittlement). (auth)
Date: February 1973
Creator: Flinn, J. E.; Krajcinovic, D.; Phipps, R. D.; Franklin, D. G. & Miller, S. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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