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Test of 6-in. -thick pressure vessels. Series 3: intermediate test vessel V-7A under sustained loading. [BWR; PWR]

Description: HSST intermediate test vessel V-7 was repaired after being tested hydrostatically to leakage and was retested pneumatically as vessel V-7A. Except for the method of applying the load, the conditions in both tests were nearly identical. In each case, a sharp outside surface flaw 547 mm long (18 in.) by about 135 mm deep (5.3 in.) was prepared in the 152-mm-thick (6-in.) test cylinder of A533, grade B, class 1 steel. The inside surface of vessel V-7A was sealed in the region of the flaw by a thin… more
Date: February 1, 1978
Creator: Bryan, R. H.; Cate, T. M.; Holz, P. P.; King, T. A.; Merkle, J. G.; Robinson, G. C. et al.
Partner: UNT Libraries Government Documents Department
open access

An experimental study of the effect of stainless steel cladding on the structural integrity of flawed steel plates in bending

Description: A small crack near the inner surface of clad nuclear reactor pressure vessels is an important consideration in the safety assessment of the structural integrity of the vessel. Experimental results from tests on large clad and unclad plate specimens with surface flaws have shown that (1) a tough surface layer composed of cladding and/or heat-affected zone has arrested running flaws in clad plates under conditions where unclad plates have ruptured, and (2) the residual load-bearing capacity of cl… more
Date: January 1, 1989
Creator: Iskander, S. K.; Nanstad, R. K.; Robinson, G. C. & Oland, C. B.
Partner: UNT Libraries Government Documents Department
open access

Pressure vessels for coal conversion systems

Description: Pressure vessels for coal conversion systems are long-lead-time, difficult-to-replace items; as suggested in some commercial conceptual designs, they will be the largest units ever fabricated anywhere in the world. They will probably be designed to Section VIII of the ASME Boiler and Pressure Vessel Code. Further, because of their size and complexity they will probably be built to the rules of Section VIII, Division 2. Economics and operating conditions will dictate that these large vessels be … more
Date: November 1, 1976
Creator: Canonico, D. A.; Robinson, G. C. & Martin, W. R.
Partner: UNT Libraries Government Documents Department
open access

Test of 6-in. -thick pressure vessels. Series 4: intermediate test vessels V-5 and V-9 with inside nozzle corner cracks. [BWR and PWR]

Description: Failure testing is described for two 99-cm-diam (39-in.), 15.2-cm-thick (6-in.) steel pressure vessels, each containing one flawed nozzle. Vessel V-5 was tested at 88/sup 0/C (190/sup 0/F) and failed by leaking without fracturing after extensive stable crack growth. Vessel V-9 was tested at 25/sup 0/C (75/sup 0/F) and failed by fracturing. Material properties measured before the tests were used for pretest and posttest fracture analyses. Test results supported by analysis indicate that inside n… more
Date: August 1, 1977
Creator: Merkle, J. G.; Robinson, G. C.; Holz, P. P. & Smith, J. E.
Partner: UNT Libraries Government Documents Department
open access

Prestressed concrete reactor vessel thermal cylinder model study

Description: The thermal cylinder experiment was designed both to provide information for evaluating the capability of analytical methods to predict the time-dependent stress-strain behavior of a /sup 1///sub 6/-scale model of the barrel section of a single-cavity prestressed concrete reactor vessel and to demonstrate the structural behavior under design and off-design thermal conditions. The model was a thick-walled cylinder having a height of 1.22 m, a thickness of 0.46 m, and an outer diameter of 2.06 m.… more
Date: May 4, 1977
Creator: Callahan, J. P.; Canonico, D. A.; Richardson, M.; Corum, J. M.; Dodge, W. G.; Robinson, G. C. et al.
Partner: UNT Libraries Government Documents Department
open access

Test of 6-in. -thick pressure vessels. Series 3: intermediate test vessel V-7. [PWR and BWR]

Description: The test of intermediate test vessel V-7 was a crack-initiation fracture test of a 152-mm-thick (6-in.), 990-mm-OD (39-in.) vessel of ASTM A533, grade B, class 1 steel plate with a sharp outside surface flaw 457 mm (18 in.) long and about 135 mm (5.3 in.) deep. The vessel was heated to 91/sup 0/C (196/sup 0/F) and pressurized hydraulically until leakage through the flaw terminated the test at a peak pressure of 147 MPa (21,350 psi). Fracture toughness data obtained by testing precracked Charpy-… more
Date: August 1, 1976
Creator: Merkle, J. G.; Robinson, G. C.; Holz, P. P.; Smith, J. E. & Bryan, R. H.
Partner: UNT Libraries Government Documents Department
open access

Test of the second model of the GCFR steam generator cavity closure plug

Description: As part of its participation in the program to develop a 300 MW(e) gas-cooled fast reactor (GCFR) demonstration power plant, the Oak Ridge National Laboratory (ORNL) is conducting a series of structural model tests. One of the tasks of the ORNL effort provides for the design, analysis and/or testing of small-scale models of the PCRV penetration closure plugs. The principal objectives are to determine structural response of the plugs to normal operating pressures and to substantial overpressuriz… more
Date: January 1, 1979
Creator: Callahan, J. P.; Robinson, G. C. & Dodge, W. G.
Partner: UNT Libraries Government Documents Department
open access

Test of small-scale central-core-cavity closure for a 300-MW(e) GCFR

Description: Under the Prestressed Concrete Reactor Vessel (PCRV) Program at the Oak Ridge National Laboratory, model tests are conducted to verify the design of the PCRV for a 300 MW(e) Gas-Cooled Fast Reactor (GCFR). Prominent features of the 1:20-scale central core cavity model included a close pitched array of fifty-five penetration tubes, forty-four segmented gusset/bearing plate assemblies, and intermeshed reinforcing steel. The closure model which was designed for a maximum cavity pressure (MCP) of 1… more
Date: January 1, 1981
Creator: Robinson, G. C.; Dougan, J. R. & Naus, D. J.
Partner: UNT Libraries Government Documents Department
open access

Test of 6-inch-thick pressure vessels. Series 2. Intermediate test vessels V-3, V-4, and V-6

Description: The second series of intermediate vessel tests were crack initiation fracture tests of 6-in.-thick 39-in.-OD steel vessels with sharp surface flaws approximately 2$sup 1$/$sub 2$ in. deep by 8 in. long in the longitudinal weld seams of the test cylinders. Fracture was initiated by means of hydraulic pressurization. One vessel was tested at each of three temperatures: 75, 130, and 190$sup 0$F. Pretest analyses were made to predict the failure pressures and strains. Fracture toughness data obtain… more
Date: November 1, 1975
Creator: Bryan, R. H.; Merkle, J. G.; Raftenberg, M. N.; Robinson, G. C. & Smith, J. E.
Partner: UNT Libraries Government Documents Department
open access

Final report on PCRV thermal cylinder axial tendon failures

Description: The post-test examination of the failed tendons from the PCRV thermal cylinder experiment has been concluded. Failures in the wires are attributed to stress-corrosion cracking. The cause of tendon failures has not been unequivocably established, but they may have been due to nitrates in the duct. The wires employed in the manufacture of the tendons will crack in less than 72 hr in a 0.2 M solution of ammonium nitrate at 70$sup 0$C. The quality of the wires is poor, and surface cracks were detec… more
Date: January 1, 1976
Creator: Canonico, D. A.; Griess, J. C. & Robinson, G. C.
Partner: UNT Libraries Government Documents Department
open access

Mustangs and Cow Horses

Description: Collection of popular folklore of Texas and Mexico, including folktales, folk songs, ballads and other information about mustangs and horses. The index begins on page 425.
Date: 2017
Creator: Dobie, J. Frank (James Frank), 1888-1964; Boatright, Mody C. & Ransom, Harry H.
Partner: UNT Press
open access

HSST pressurized-thermal-shock experiment, PTSE-1. [PWR; BWR]

Description: The first pressurized-thermal-shock experiment (PTSE-1) in the Heavy-Section Steel Technology (HSST) Program is the most recent of a long successtion of fracture-mechanics experiments that are on a scale that allows important aspects of fracture behavior of reactor pressure vessels to be simulated. Such experiments are the means by which theoretical models of fracture behavior can be evaluated for possible aplication to fracture analysis of vessels in nuclear plants. The principal issues of con… more
Date: January 1, 1984
Creator: Bryan, R. H.; Bass, B. R.; Robinson, G. C.; Merkle, J. G.; Whitman, G. D. & Pugh, C. E.
Partner: UNT Libraries Government Documents Department
open access

Performance of low upper-shelf material under pressurized-thermal-shock loading (PTSE-2)

Description: The second pressurized-thermal-shock experiment (PTSE-2) of the Heavy-Section Steel Technology Program was conceived to investigate fracture behavior of steel with low ductile-tearing resistance. PTSE-2 was designed primarily to reveal the interaction of ductile and brittle modes of fracture and secondarily to investigate the effects of warm prestressing. A test vessel was prepared by inserting a crack-like flaw of well-defined geometry on the outside surface of the vessel. The flaw was 1 m lon… more
Date: January 1, 1987
Creator: Bryan, R. H.; Bass, B. R.; Bolt, S. E.; Bryson, J. W.; Corwin, W. R.; Nanstad, R. K. et al.
Partner: UNT Libraries Government Documents Department
open access

Pressurized-thermal-shock experiments: PTSE-1 results and PTSE-2 plans

Description: The first pressurized-thermal-shock experiment (PTSE-1) was performed with a vessel with a 1-m-long flaw in a plug of specially tempered steel having the composition of SA-508 forging steel. The second experiment (PTSE-2) will have a similar arrangement, but the material in which the flaw will be implanted is being prepared to have low tearing resistance. Special tempering of a 2 1/4 Cr - 1 Mo steel plate has been shown to induce a low Charpy impact energy in the upper-shelf temperature range. … more
Date: January 1, 1985
Creator: Bryan, R. H.; Nanstad, R. K.; Wanner, R.; Merkle, J. G.; Robinson, G. C. & Whitman, G. D.
Partner: UNT Libraries Government Documents Department
open access

Results and conclusions from the first pressurized-thermal-shock experiment. [Overcooling]

Description: Pretest estimates of fracture toughness are reasonably close to the PTSE-1 values. Furthermore, the ASME Sect. XI toughness relationships are conservative relative to actual material characteristics. The experiment demonstrated that arrest toughness substantially above the 220 MPa...sqrt..m cutoff of Sect. XI could be realized. The arrest values in PTSE-1 also are consistent with arrest measurements made in wide-plate tests and reported by the Japan Welding Council. The highest PTSE-1 value of … more
Date: January 1, 1984
Creator: Bryan, R. H.; Bolt, S. E.; Merkle, J. G.; Bass, B. R.; Bryson, J. W.; Robinson, G. C. et al.
Partner: UNT Libraries Government Documents Department
open access

Pressurized-thermal-shock experiments with thick vessels

Description: Information is provided on the series of pressurized-thermal-shock experiments at the Oak Ridge National Laboratory, motivated by a concern for the behavior of flaws in reactor pressure vessels having welds or shells exhibiting low upper-shelf Charpy impact energies, approx. 68J or less. (JDB)
Date: January 1, 1986
Creator: Bryan, R. H.; Nanstad, R. K.; Merkle, J. G.; Robinson, G. C. & Whitman, G. D.
Partner: UNT Libraries Government Documents Department
open access

Mustangs and Cow Horses

Description: Collection of popular folklore of Texas and Mexico, including folktales, folk songs, ballads and other information about mustangs and horses. The index begins on page 425.
Date: 1940
Creator: Dobie, J. Frank (James Frank), 1888-1964; Boatright, Mody C. & Ransom, Harry H.
Partner: UNT Press
open access

Final report of comprehensive testing program for concrete at elevated temperatures

Description: The objective of this program was to define the variations in physical (thermal) and mechanical (strength) properties of limestone aggregate concrete and lightweight insulating concrete exposed to elevated temperatures that could occur as a result of a postulated large sodium spill in a lined LMFBR equipment cell. To meet this objective, five test series were conducted: (1) unconfined compression, (2) shear, (3) rebar bond, (4) sustained loading (creep), and (5) thermal properties. Mechanical p… more
Date: October 1, 1980
Creator: Oland, C. B.; Naus, D. J. & Robinson, G. C.
Partner: UNT Libraries Government Documents Department
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