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Central Calorimeter Support Cradle Jack Failure Analysis

Description: The Central Calorimeter and its support cradle are to be supported by either hydraulic or mechanical jacks. If hydraulics are used, each support will use two hydraulically coupled jacks with two out of the four supports hydraulically coupled giving the effect of a three point support system. If mechanical jacks are used, all four points are used for support. Figure 2 shows two examples of jack placement on a 3.5 inch support plate. These two support scenarios lead to five jack failure cases to be studied. This report deals with the way in which a 0.25 inch drop (failed jack) at one support affects the stresses in the cradle. The stresses from each failure case were analyzed in two ways. First, stress factors, defined as quotients of stress intensities of the failed case with respect to the static case, were generated and then, hand calculations similar to those in Engineering Note 3740.215-EN-14 were done using the reaction forces from the failed case.
Date: April 10, 1987
Creator: Rudland, D.L.
Partner: UNT Libraries Government Documents Department

Central Calorimeter Thermal Gradient Module Connection Analysis

Description: Two 20 kW condensing and one 10 kW steady state cooling coils will be used to cool and condense gaseous argon in the Central Calorimeter (CC) Cryostat. Since this cool down (300K to 90K) will inevitably cause shrinkage in the modules contained inside the cryostat, the connections between the modules have to be designed to withstand the increase in forces and moments induced by this contraction. This paper presents finite element analysis (ANSYS{reg_sign}) results to aid in the design or modification of the Central Calorimeter module connections.
Date: August 7, 1987
Creator: Rudland, D.L.
Partner: UNT Libraries Government Documents Department

Flexible Support Liquid Argon Heat Intercept

Description: A device in the flexible support system for the Central Calorimeter is the Liquid Argon Heat Intercept. The purpose of this apparatus is to intercept heat outside the inner vessel so that bubbles do not form inside. If bubbles did happen to form inside the vessel, they would cause an electric arc between the read-out board and the absorption plates, thus destroying the pre-amplifier. Since this heat intercept is located in the center of the flexible support, it must also support the load of the Central Caloimeter. Figure 1 shows how the intercept works. The subcooled liquid argon is driven through a 1/4-inch x 0.049-inch w tube by hydrostatic pressure. the ambient heat boils the subcooled argon. The gaseous argon flows through the tube and is condensed at the top of the vessel by a 100 kW cooling coil. This process is rpesent in all four flexible support systems.
Date: May 18, 1987
Creator: Rudland, D.L.
Partner: UNT Libraries Government Documents Department

Flexible Support Stanchion

Description: Figure 1 shows the assembly drawing of the Central Calorimeter Cryostat Flexible Support Stanchion. Figures 2 and 3 show the Flexible Support STanchion in detail. These Stanchions support the cryostat safely, reduce the heat load to the cryostat from the ambient by a factor of more than ten, provide a spring like action that reduce the loads created by thermal contraction of the cryostat and position the cryostate accurately. Table 1 shows all of the details of the Flexible Support system for the C.C. Cryostat.
Date: May 11, 1987
Creator: Rudland, D.L.
Partner: UNT Libraries Government Documents Department

Fracture toughness evaluations of TP304 stainless steel pipes

Description: In the IPIRG-1 program, the J-R curve calculated for a 16-inch nominal diameter, Schedule 100 TP304 stainless steel (DP2-A8) surface-cracked pipe experiment (Experiment 1.3-3) was considerably lower than the quasi-static, monotonic J-R curve calculated from a C(T) specimen (A8-12a). The results from several related investigations conducted to determine the cause of the observed toughness difference are: (1) chemical analyses on sections of Pipe DP2-A8 from several surface-cracked pipe and material property specimen fracture surfaces indicate that there are two distinct heats of material within Pipe DP2-A8 that differ in chemical composition; (2) SEN(T) specimen experimental results indicate that the toughness of a surface-cracked specimen is highly dependent on the depth of the initial crack, in addition, the J-R curves from the SEN(T) specimens closely match the J-R curve from the surface-cracked pipe experiment; (3) C(T) experimental results suggest that there is a large difference in the quasi-static, monotonic toughness between the two heats of DP2-A8, as well as a toughness degradation in the lower toughness heat of material (DP2-A8II) when loaded with a dynamic, cyclic (R = {minus}0.3) loading history.
Date: February 1, 1997
Creator: Rudland, D.L.; Brust, F.W. & Wilkowski, G.M.
Partner: UNT Libraries Government Documents Department

The effect of cyclic and dynamic loads on carbon steel pipe

Description: This report presents the results of four 152-mm (6-inch) diameter, unpressurized, circumferential through-wall-cracked, dynamic pipe experiments fabricated from STS410 carbon steel pipe manufactured in Japan. For three of these experiments, the through-wall crack was in the base metal. The displacement histories applied to these experiments were a quasi-static monotonic, dynamic monotonic, and dynamic, cyclic (R = {minus}1) history. The through-wall crack for the third experiment was in a tungsten-inert-gas weld, fabricated in Japan, joining two lengths of STS410 pipe. The displacement history for this experiment was the same history applied to the dynamic, cyclic base metal experiment. The test temperature for each experiment was 300 C (572 F). The objective of these experiments was to compare a Japanese carbon steel pipe material with US pipe material, to ascertain whether this Japanese steel was as sensitive to dynamic and cyclic effects as US carbon steel pipe. In support of these pipe experiments, quasi-static and dynamic, tensile and fracture toughness tests were conducted. An analysis effort was performed that involved comparing experimental crack initiation and maximum moments with predictions based on available fracture prediction models, and calculating J-R curves for the pipe experiments using the {eta}-factor method.
Date: February 1, 1996
Creator: Rudland, D.L.; Scott, P.M. & Wilkowski, G.M.
Partner: UNT Libraries Government Documents Department

The effects of cyclic and dynamic loading on the fracture resistance of nuclear piping steels. Technical report, October 1992--April 1996

Description: This report presents the results of the material property evaluation efforts performed within Task 3 of the IPIRG-2 Program. Several related investigations were conducted. (1) Quasi-static, cyclic-load compact tension specimen experiments were conducted using parameters similar to those used in IPIRG-1 experiments on 6-inch nominal diameter through-wall-cracked pipes. These experiments were conducted on a TP304 base metal, an A106 Grade B base metal, and their respective submerged-arc welds. The results showed that when using a constant cyclic displacement increment, the compact tension experiments could predict the through-wall-cracked pipe crack initiation toughness, but a different control procedure is needed to reproduce the pipe cyclic crack growth in the compact tension tests. (2) Analyses conducted showed that for 6-inch diameter pipe, the quasi-static, monotonic J-R curve can be used in making cyclic pipe moment predictions; however, sensitivity analyses suggest that the maximum moments decrease slightly from cyclic toughness degradation as the pipe diameter increases. (3) Dynamic stress-strain and compact tension tests were conducted to expand on the existing dynamic database. Results from dynamic moment predictions suggest that the dynamic compact tension J-R and the quasi-static stress-strain curves are the appropriate material properties to use in making dynamic pipe moment predictions.
Date: December 1, 1996
Creator: Rudland, D.L.; Brust, F. & Wilkowski, G.M.
Partner: UNT Libraries Government Documents Department