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Stress analysis of ultrasonic density detector for LOFT core inlet steady-state and LOCE conditions. Supplement 1

Description: The UDD sensor bar with modified cross-section (0.0938-in. thick by 0.25-in. high overall) was analyzed to determine its resonant frequencies. Thermal and fluid-induced stresses due to steady-state and LOCE loads were also calculated. The sensor bar was shown not to be subject to vortex-shedding lock-in and was shown to meet applicable criteria of the ASME Boiler and Pressure Vessel Code. Seismic loads are insignificant compared to fluid loads.
Date: April 25, 1979
Creator: Mosby, W.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Evaluation of cracking in feedwater piping adjacent to the steam generators in Nine Pressurized Water Reactor Plants

Description: Cracking in ASTM A106-B and A106-C feedwater piping was detected near the inlet to the steam generators in a number of pressurized water reactor plants. We received sections with cracks from nine of the plants with the objective of identifying the cracking mechanism and assessing various factors that might contribute to this cracking. Variations were observed in piping surface irregularities, corrosion-product, pit, and crack morphology, surface elmental and crystal structure analyses, and stee… more
Date: June 25, 1980
Creator: Goldberg, A.; Streit, R. D. & Scott, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Study of safety relief valve operation under ATWS conditions. [Super critical flow]

Description: In March 1979, ETEC published as ETEC-TDR-78-19 a search which updated earlier NRC studies of saturated or subcooled water flow through relief valves, under ATWS conditions. This Supplement expands upon that search to include supercritical steam-water flow. No applicable data for the supercritical conditions was found, nor were any newer data on saturated or subcooled conditions uncovered. The Supplement also updated a look for facilities currently capable of simultaneously imposing all ATWS co… more
Date: July 25, 1979
Creator: Hutmacher, E. S. & Whitten, S. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Study of safety relief valve operation under ATWS conditions. [PWR]

Description: A literature survey and analysis project has been performed to determine if recent (since mid-1975) data has been reported which could influence the current approach to predicting PWR relief valve capacity under ATWS conditions. This study was conducted by the Energy Technology Engineering Center for NRC. Results indicate that the current relief valve capacity model tends to predict less capacity than actually obtains; however, no experimental verification at PWR ATWS conditions was found. Othe… more
Date: June 25, 1979
Creator: Hutmacher, E. S.; Nesmith, B. J. & Brukiewa, J. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Evaluation and demonstration of methods for improved fuel utilization. First semi-annual progress report, September 1979-March 1980

Description: Demonstrations of improved fuel management and burnup are being performed in the Fort Calhoun reactor. More efficient fuel management will be achieved through the implementation of a low leakage concept called SAVFUEL (Shimmed And Very Flexible Uranium Element Loading), which is expected to reduce uranium requirements by 2 to 4%. The burnup will be increased sufficiently to reduce uranium requirements by 5 to 15%. Four fuel assemblies scheduled to demonstrate the SAVFUEL duty cycle and loaded i… more
Date: June 25, 1980
Creator: Decher, U.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

THERMAL HISTORY OF CLADDING IN A 21 PWR WASTE PACKAGE LOADED WITH AVERAGE FUEL

Description: The purpose of this calculation is to evaluate a mid-assembly axial fuel cladding temperature profile of a 21 pressurized water reactor (PWR) spent nuclear fuel (SNF) waste package (WP) loaded with average fuel assemblies and emplaced in a monitored geologic repository. This calculation is intended to evaluate Viability Assessment (VA) and Enhanced Design Alternatives (EDA) II design configurations in support of performance assessment. This calculation was developed by Waste Package Operations … more
Date: January 25, 2000
Creator: Wade, H.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Tabulation of Fundamental Assembly Heat and Radiation Source Files

Description: The purpose of this calculation is to tabulate a set of computer files for use as input to the WPLOAD thermal loading software. These files contain details regarding heat and radiation from pressurized water reactor (PWR) assemblies and boiling water reactor (BWR) assemblies. The scope of this calculation is limited to rearranging and reducing the existing file information into a more streamlined set of tables for use as input to WPLOAD. The electronic source term files used as input to this ca… more
Date: October 25, 2006
Creator: deBues, T. & Ryman, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reexamination of spent fuel shipment risk estimates

Description: The risks associated with the transport of spent nuclear fuel by truck and rail have been reexamined and compared to results published in NUREG-O170 and the Modal Study. The full reexamination considered transport of PWR and BWR spent fuel by truck and rail in four generic Type B spent fuel casks. Because they are typical, this paper presents results only for transport of PWR spent fuel in steel-lead steel casks. Cask and spent fuel response to collision impacts and fires were evaluated by perf… more
Date: April 25, 2000
Creator: Cook, J. R. & Sprung, Jeremy L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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