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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

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

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