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Supplementary information on Series II Test A-5 test conditions

Description: Test planning and test preparation for LLTR Series II Test A-5 are continuing at GE and ETEC. The main objective for this test is to obtain data on the type and magnitude of steam tube blowout failures resulting from worst case leak conditions under the superheater hot standby condition (i.e., the plant condition considered most susceptible to steam tube blowout failures from wastage/overheating). A corollary objective is to add large quantities of steam (i.e. approx. 330 lbs) to simulate the amount that could be added in a plant system (such as CRBRP) before pressure would build up in the intermediate Heat Transport System to blow the expansion tank rupture disc. This report recommends the preferred method for operating the LLTR primary/secondary steam systems for Test A-5. i.e., Option 5 - Common Supply Tanks for Primary and Secondary Systems.
Date: November 16, 1981
Partner: UNT Libraries Government Documents Department

RODCON: a finite difference heat conduction computer code in cylindrical coordinates

Description: RODCON, a finite difference computer code, was developed to calculate the internal temperature distribution of the fuel rod simulator (FRS) for the Core Flow Test Loop (CFTL). RODCON solves the implicit, time-dependent forward-differencing heat transfer equation in 2-dimensional (Rtheta) cylindrical coordinates at an axial plane with user specified radial material zones and surface conditions at the FRS periphery. Symmetry of the boundary conditions of coolant bulk temperatures and film coefficients at the FRS periphery is not necessary.
Date: September 16, 1980
Creator: Conklin, J.C.
Partner: UNT Libraries Government Documents Department

Breeder reactor fuel fabrication system development

Description: Significant progress has been made in the design and development of remotely operated breeder reactor fuel fabrication and support systems (e.g., analytical chemistry). These activities are focused by the Secure Automated Fabrication (SAF) Program sponsored by the Department of Energy to provide: a reliable supply of fuel pins to support US liquid metal cooled breeder reactors and at the same time demonstrate the fabrication of mixed uranium/plutonium fuel by remotely operated and automated methods.
Date: July 16, 1981
Creator: Bennett, D.W.; Fritz, R.L.; McLemore, D.R. & Yatabe, J.M.
Partner: UNT Libraries Government Documents Department

Comparative analysis of internal fuel motion in annular fuel designs

Description: In this paper, the whole-core reactivity consequences of internal fuel motion in three annular fuel designs during a hypothetical 3 dollars/s transient overpower (TOP) accident are compared to determine the effect of geometric design variations. The PINEX-2 and PINEX-3 experiments were performed in the TREAT reactor using annular fuel pins irradiated in GETR. This paper investigates three combinations of solid and annular axial blankets and fission gas plena: top annular blanket and plenum, bottom annular blanket and plenum, and both top and bottom (dual) annular blankets and plena. The dual plena design case showed a significant decrease in internal fuel motion over the single plenum design cases.
Date: September 16, 1983
Creator: Smith, D.E.
Partner: UNT Libraries Government Documents Department

Nuclear reactor control apparatus. [FBR]

Description: Nuclear reactor safety rod release apparatus comprises a ring which carries detents normally positioned in an annular recess in outer side of the rod, the ring being held against the lower end of a drive shaft by magnetic force exerted by a solenoid carried by the drive shaft. When the solenoid is de-energized, the detent-carrying ring drops until the detents contact a cam surface associated with the lower end of the drive shaft, at which point the detents are cammed out of the recess in the safety rod to release the rod from the drive shaft. In preferred embodiments of the invention, an additional latch is provided to release a lower portion of a safety rod under conditions that may interfere with movement of the entire rod.
Date: April 16, 1981
Creator: Sridhar, B.N.
Partner: UNT Libraries Government Documents Department

Inventory and relative biological hazard of LMFBR core materials

Description: Information on the composition of an LMFBR core by element has been collected on the basis of published design data and ORIGEN calculations. The mass quantities of structural materials, actinides, and fission products are in the ratio of 1:1.4:0.1 with actinides, particularly plutonium and neptunium, representing the major inhalation and ingestion hazard. Some of the fission products are present in quantities large enough to suggest that they warrant specific attention in source term analysis.
Date: January 16, 1978
Creator: Tobias, M.L.
Partner: UNT Libraries Government Documents Department

Gas-Cooled Reactors: the importance of their development

Description: Gas-Cooled Reactors are considered to have a significant future impact on the application of fission energy. The specific types are the steam-cycle High-Temperature Gas-Cooled Reactor, the Gas-Cooled Fast Breeder Reactor, the gas-turbine HTGR, and the Very High-Temperature Process Heat Reactor. The importance of developing the above systems is discussed relative to alternative fission power systems involving Light Water Reactors, Heavy Water Reactors, Spectral Shift Controlled Reactors, and Liquid-Metal-Cooled Fast Breeder Reactors. A primary advantage of developing GCRs as a class lies in the technology and cost interrelations, permitting cost-effective development of systems having diverse applications. Further, HTGR-type systems have highly proliferation-resistant characteristics and very attractive safety features. Finally, such systems and GCFRs are mutally complementary. Overall, GCRs provide interrelated systems that serve different purposes and needs; their development can proceed in stages that provide early benefits while contributing to future needs. It is concluded that the long-term importance of the various GCRs is as follows: HTGR, providing a technology for economic GCFRs and HTGR-GTs, while providing a proliferation-resistant reactor system having early economic and fuel utilization benefits; GCFR, providing relatively low cost fissile fuel and reducing overall separative work needs at capital costs lower than those for LMFBRs; HTGR-GT (in combination with a bottoming cycle), providing a very high thermal efficiency system having low capital costs and improved fuel utilization and technology pertinent to VHTRs; HTGR-GT, providing a power system well suited for dry cooling conditions for low-temperature process heat needs; and VHTR, providing a high-temperature heat source for hydrogen production processes.
Date: November 16, 1978
Creator: Kasten, P.R.
Partner: UNT Libraries Government Documents Department

Design and operation of a rapid thermal transient component testing sodium loop

Description: A specific problem developed during the design of an on-line sampling system for the Sodium Loop Safety Facility fast breeder reactor experiments. Rapid fluctuations in the sodium temperature, caused by reactor operation and shutdown, exposed the system components to conditions that could result in fatigue failure. A component test loop was designed and built at the Idaho National Engineering Laboratory to allow experimental qualification of component integrity. This paper outlines test system requirements, describes the design and special features, presents test procedures ad relates significant operating experience.
Date: April 16, 1984
Creator: Crandall, D.L.
Partner: UNT Libraries Government Documents Department

Diffusion bonding resistant valve development for sodium service

Description: Unanticipated functional failures occurred in valves undergoing containment integrity testing for liquid sodium service. The failures resulted from diffusion bonding of the Stellite 6B valve plug to the Type 316 stainless steel (SS) seat. As a result of these failures, a valve development program was undertaken. A modified valve incorporating a Tribaloy 800 plug showed significant improvement in resistance to diffusion bonding but still failed after long term exposure in a closed position. A second modified valve using Tribaloy 800 in both the valve plug and seat successfully resisted diffusion bonding failure. This paper reports the details of the testing and posttest valve examinations. The results of scanning electron microscopy, dispersive x-ray spectrometry, and metallography provide the characteristics of the valve failures. Limitations of the various valve designs are also discussed.
Date: April 16, 1984
Creator: Crandall, D.L.; Low, J.O.; Chung, D.T. & Loop, R.B.
Partner: UNT Libraries Government Documents Department