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Inelastic analysis of two plates under deformation dependent loads

Description: Cover plates are used in current designs for high temperature gas-cooled reactors to compress the mineral fiber insulation against the inside of the liner of the prestressed concrete pressure vessel. In the upper plenum, these plates are hexagonal and specified as carbon steel; in the lower cross ducts, the plates are square and made of Hastelloy X. The General Atomic Company has specified both damage and safety limit criteria for these plates. These plates have been analyzed at these limits using the inelastic finite element computer program EPACA. The results indicate that the total strains for the square plate were within the specified values; however, the maximum deformations at the free corners indicate separation from the insulation and failure to achieve one of the design requirements. Since no material data were available for carbon steel at the limiting temperatures, it was assumed that the hexagonal plates were constructed of 2$sup 1$/$sub 4$ percent Cr--1 percent Mo material. Although this material was found to produce satisfactory performance, extrapolation of available information would lead to the conclusion that the performance of carbon steel plates would not be satisfactory at the specified conditions. (auth)
Date: February 1, 1976
Creator: Iskander, S.K.; Collins, C.W. & Sanders, J.P.
Partner: UNT Libraries Government Documents Department

CACA-2: revised version of CACA-a heavy isotope and fission-product concentration calculational code for experimental irradiation capsules

Description: A computer program is described which calculates nuclide concentration histories, power or neutron flux histories, burnups, and fission-product birthrates for fueled experimental capsules subjected to neutron irradiations. Seventeen heavy nuclides in the chain from $sup 232$Th to $sup 242$Pu and a user- specified number of fission products are treated. A fourth-order Runge-Kutta calculational method solves the differential equations for nuclide concentrations as a function of time. For a particular problem, a user-specified number of fuel regions may be treated. A fuel region is described by volume, length, and specific irradiation history. A number of initial fuel compositions may be specified for each fuel region. The irradiation history for each fuel region can be divided into time intervals, and a constant power density or a time-dependent neutron flux is specified for each time interval. Also, an independent cross- section set may be selected for each time interval in each irradiation history. The fission-product birthrates for the first composition of each fuel region are summed to give the total fission-product birthrates for the problem.
Date: February 1, 1976
Creator: Allen, E.J.
Partner: UNT Libraries Government Documents Department

January 1976 monthly highlights for Office of Nuclear Regulatory Research Programs at Oak Ridge National Laboratory

Description: Technical highlights and cost/budget data are presented for the following programs: heavy section steel technology, fission product beta and gamma energy release, LOCA release from LWR fuel, multirod burst tests, Nuclear Safety Information Center, PWR blowdown heat transfer-separate effects, Zircaloy fuel cladding collapse studies, zirconium metal-water oxidation kinetics, aerosol release and transport from LMFBR fuel, HTGR safety analysis and research, and design criteria for piping and nozzles.
Date: February 1, 1976
Creator: Fee, G. G.
Partner: UNT Libraries Government Documents Department

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 detected. These could have acted as concentrating sites for both stress and the deleterious contaminants. It is believed that the factors that led to the failures in the thermal cylinder experiment were unique. An improper formulation of the epoxy resin did not provide the tendon anchor plate seal that was desired; indeed, the improper formulation is responsible for the high level of nitrogen in the ducts of the failed tendons. (auth)
Date: January 1, 1976
Creator: Canonico, D.A.; Griess, J.C. & Robinson, G.C.
Partner: UNT Libraries Government Documents Department

Quarterly progress report on high-temperature gas-cooled reactor safety studies sponsored by the NRC Division of Reactor Safety Research for October--December 1975

Description: Research progress is briefly reported for the following tasks: reheater and steam generator model development, development of the nuclear steam supply system simulation code, core simulation for enemergency cooling analysis, core auxiliary cooling system model development, and computer code implementation.
Date: February 1, 1976
Creator: Sanders, J.P.
Partner: UNT Libraries Government Documents Department

Monthly progress report for January 1976 for the HTGR safety studies for the Division of Systems Safety, U.S. Nuclear Regulatory Commission

Description: Progress is reported in the areas of thermal analysis of HTGR systems, axial mode spacing affects in flow distribution calculations, and performance calculations for the core auxiliary heat exchanger.
Date: February 1, 1976
Creator: Sanders, J.P.
Partner: UNT Libraries Government Documents Department

Monthly progress report for December 1975 for the HTGR safety studies for the Division of Technical Review U.S. Nuclear Regulatory Commission

Description: Brief highlights are presented for the following activities: HEXERI code development; FLOOIS code development; analysis of thermal barrier cover plates; and determination of physical property values for helium-air mixtures. (JWR)
Date: January 1, 1976
Creator: Sanders, J.P.
Partner: UNT Libraries Government Documents Department