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Water Reactor Safety Research Division. Quarterly progress report, April 1-June 30, 1980

Description: The Water Reactor Safety Research Programs quarterly report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the USNRC Division of Reactor Safety Research. The projects reported each quarter are the following: LWR Thermal Hydraulic Development, Advanced Code Evlauation, TRAC Code Assessment, and Stress Corrosion Cracking of PWR Steam Generator Tubing.
Date: August 1, 1980
Creator: Abuaf, N.; Levine, M. M.; Saha, P. & van Rooyen, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Downflow heat transfer in a heated ribbed vertical annulus with a cosine power profile

Description: Experiments designed to investigate downflow heat transfer in a heated, ribbed annulus test section simulating one of the annular coolant channels of a Savannah River Plant production reactor Mark 22 fuel assembly have been conducted at the Idaho National Engineering Laboratory. The inner surface of the annulus was constructed of aluminum and was electrically heated to provide an axial cosine power profile and a flat azimuthal power shape. Data presented in this report are from the ECS-2c serie… more
Date: October 1, 1991
Creator: Anderson, J. L.; Condie, K. G. & Larson, T. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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NaK pool-boiler bench-scale receiver durability test: Test results and materials analysis

Description: Pool-boiler reflux receivers have been considered as an alternative to heat pipes for the input of concentrated solar energy to Stirling-cycle engines in dish-Stirling electric generation systems. Pool boilers offer simplicity in design and fabrication. The operation of a full-scale pool-boiler receiver has been demonstrated for short periods of time. However, to generate cost-effective electricity, the receiver must operate Without significant maintenance for the entire system life, as much as… more
Date: June 1, 1994
Creator: Andraka, C. E.; Goods, S. H.; Bradshaw, R. W.; Moreno, J. B.; Moss, T. A. & Jones, S. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Durability of containers for storing solidified radioactive wastes. [Cor-Ten A]

Description: Most concepts for the disposal of highly radioactive waste involve converting the waste to a solid form like concrete or glass and storing this solid form in metal containers. Two major factors in the final selection of materials for these containers are the compatibility between waste form and container material and the durability of the material at temperatures and stresses expected during service and possible accidents. Currently, AISI 1020 carbon steel appears to be a better material than o… more
Date: January 1, 1976
Creator: Angerman, C. L. & Rankin, W. N.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Investigation of Minimum Film boiling Phenomena on Fuel Rods Under Blowdown Cooling Conditions

Description: Blowdon cooling heat transfer is an important process that occurs early in a hypothetical large break loss-of-coolant accident (LOCA) in a pressurized water reactor. During blowdown, the flow through the hot assembly is a post-critical heat flux dispersed droplet flow. The heat transfer mechanisms that occur in blowdown cooling are complex and depend on droplet and heated surface interaction. In a safety analysis, it is of considerable importance to determine the thermal-hydraulic conditions le… more
Date: July 2002
Creator: Bajorek, Stephen M.; Gawron, Michael; Etzel, Timothy & Peterson, Lucas
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Electrochemical and metallurgical aspects of stress corrosion cracking of sensitized Alloy 600 in simulated primary water containing sulfur contamination

Description: The stress corrosion cracking (SCC) of sensitized Alloy 600 was investigated in aerated solutions of sodium thiosulfate containing 1.3% boric acid. Results indicate that in the borated thiosulfate solution containing 7 ppM sulfur, 5 ppM lithium as lithium hydroxide is sufficient to inhibit SCC in U-bends. The occurrence of inhibition seems to correlate to the rapid increase of pH and conductivity of the solution as a result of the lithium hydroxide addition. In the slow strain rate tests in the… more
Date: January 1, 1985
Creator: Bandy, R. & Kelly, K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Effect of thermal stabilization on the low-temperature stress-corrosion cracking of Inconel 600

Description: The propensity to low-temperature stress-corrosion cracking (SCC) of thermally stabilized Inconel 600 in sulfur-bearing environments has been investigated using U-bends and slow-strain-rate testing. The results have been compared with those of sensitized Inconel 600. The potential dependence of crack-propagation rate has been established in a single test by using several U-bends held at different potentials, by choosing an appropriate electrical circuitry. The difference in SCC susceptibility o… more
Date: January 1, 1983
Creator: Bandy, R. & van Rooyen, D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Initiation and propagation of stress-corrosion cracking of Alloy 600 in high-temperature water. [PWR]

Description: Results of stress-corrosion cracking data are presented for Inconel 600 steam-generator tubing. U-bend, constant-load, and slow extension-rate tests are included. Arrhenius plots are presented for failure times vs inverse temperature for crack initiation and propagation. Effect of applied load is expressed in terms of log-log curves for failure times vs stress, and variations in environment and cold work are included. Microstructure and composition of oxide films on Inconel 600 surfaces were ex… more
Date: January 1, 1983
Creator: Bandy, R. & van Rooyen, D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Mechanisms of stress corrosion cracking and intergranular attack in Alloy 600 in high temperature caustic and pure water

Description: In recent years, several studies have been conducted on the intergranular stress corrosion cracking (SCC) and intergranular attack (IGA) of Alloy 600. A combination of SCC and IGA has been observed in Alloy 600 tubing on the hot leg of some operating steam generators in pressurized water reactor (PWR) nuclear power plants, and sodium hydroxide along with several other chemical species have been implicated in the tube degradations. SCC has been observed above and within the tube sheet, whereas I… more
Date: January 1, 1984
Creator: Bandy, R. & van Rooyen, D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Stress-corrosion cracking of Inconel alloy 600 in high-temperature water: an update. [PWR]

Description: Inconel 600 has been tested in high-temperature aqueous media (without oxygen) in several tests. Data are presented to relate failure times to periods of crack initiation and propagation. Quantitative relationships have been developed from tests in which variations were made in temperature, applied load, strain rate, water chemistry, and the condition of the test alloy.
Date: January 1, 1983
Creator: Bandy, R. & van Rooyen, D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Tests with Inconel 600 to obtain quantitative stress-corrosion cracking data for evaluating service performance. [PWR]

Description: Inconel 600 tubes in pressurized water reactor (PWR) steam generators form a pressure boundary between radioactive primary water and secondary water which is converted to steam and used for generating electricity. Under operating conditions the performance of alloy 600 has been good, but with some occasional small leaks resulting from stress corrosion cracking (SCC), related to the presence of unusually high residual or operating stresses. The suspected high stresses can result from either the … more
Date: September 1, 1982
Creator: Bandy, R. & van Rooyen, D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Intergranular failures of Alloy 600 in high temperature caustic environments

Description: This paper describes the results of our investigation of two commonly observed modes of failure of Alloy 600 in high temperature caustic environment namely, intergranular stress corrosion cracking (IGSCC) and intergranular attack (IGA). Specimens are studied as C-rings under constant deflection, wires with and without any externally applied load, and as straining electrodes. The potential dependence of average crack propagation rate is established in a single test by using several C-rings held … more
Date: January 1, 1984
Creator: Bandy, R.; Roberge, R. & van Rooyen, D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Evaluation of the Initial Isothermal Physics Measurements at the Fast Flux Test Facility, a Prototypic Liquid Metal Fast Breeder Reactor

Description: The Fast Flux Test Facility (FFTF) was a 400-MWt, sodium-cooled, low-pressure, high-temperature, fast-neutron flux, nuclear fission reactor plant designed for the irradiation testing of nuclear reactor fuels and materials for the development of liquid metal fast breeder reactors (LMFBRs). The FFTF was fueled with plutonium-uranium mixed oxide (MOX) and reflected by Inconel-600. Westinghouse Hanford Company operated the FFTF as part of the Hanford Engineering Development Laboratory (HEDL) for th… more
Date: March 1, 2010
Creator: Bess, John D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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