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Removal of the Materials Test Reactor overhead working reservoir

Description: Salient features of the removal of an excessed contaminated facility, the Materials Test Reactor (MTR) overhead working reservoir (OWR) from the Test Reactor Area to the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory are described. The 125-ton OWR was an overhead 160,000- gallon-capacity tank approximately 193 feet high which supplied cooling water to the MTR. Radiation at ground level beneath the tank was 5 mR/hr and approximately 600 mR/hr at the exterior surface of the tank. Sources ranging from 3 R/hr to in excess of 500 R/hr exist within the tank. The tank interior is contaminated with uranium, plutonium, and miscellaneous fission products. The OWR was lowered to ground level with the use of explosive cutters. Dismantling, decontamination, and disposal were performed by Aerojet Nuclear Company maintenance forces. (auth)
Date: October 1, 1975
Creator: Lunis, B.C.
Partner: UNT Libraries Government Documents Department

Steady-state creep model for UO$sub 2$

Description: From a review of out-of-pile and in-pile experiments, an analytical model was developed for the steady-state creep of UO$sub 2$: epsilon = [(A$sub 1$ - A$sub 2$F)sigma e/sup -Q$sub 1$/RT/]/[A$sub 3$ + D)G$sup 2$] + [A$sub 4$sigma/ sup 4.5/e/sup -Q$sub 2$/RT/]/[(A$sub 5$ + D)] + A$sub 6$sigma Fe/sub-Q$sub 3$/RT/ , where A$sub 1$ = 9.728 x 10$sup 6$, A$sub 2$ = 3.24 x 10$sup -12$, A$sub 3$ = - 87.7, A$sub 4$ = 1.376 x 10$sup -4$, A$sub 5$ = -90.5, A$sub 6$ = 9.24 x 10$sup - 28$, Q$sub 1$ = 90,000, Q$sub 2$ = 132,000, Q$sub 3$ = 5200 (cal/mole), F = fission rate (8.4 x 10$sup 17$ to 1.18 x 10$sup 20$ f/m$sup 3$s), and G = grain size. (DLC)
Date: January 1, 1975
Creator: Olsen, C.S.
Partner: UNT Libraries Government Documents Department

Transient propagation behavior of two-phase flow equations

Description: The capability of published two-phase flow equation sets to predict transient propagation behavior has been studied numerically. The equation sets are those cited by Wallis for separated flow and extensions of those used by Rudinger and Chang for dispersed flow. The primary difference between these two sets is that in the set cited by Wallis, the pressure gradient appearing in each momentum equation is weighted by the phase volume fraction, whereas in the extended Rudinger--Chang set, the pressure gradient appears only in the ''continuous'' phase. The original Rudinger--Chang set had to be modified because it can adequately describe only the transient flow of very dilute suspensions of solids in air. This numerical study shows that pressure pulses propagate at essentially the sound speeds obtained from characteristics analysis for the equation sets investigated. Comparisons of numerical results with experimental air-water pressure propagation data show that only the modified Rudinger--Chang equation set exhibits propagation behavior in good agreement with the experimental observations at low (less than 10 percent) void fractions. None of the equation sets adequately predict the experimental pressure propagation rates in the range of void fractions from 10 to 60 percent where the flow regime was observed to change from bubbly to full slug flow. The modified Rudinger-- Chang set explains an apparent discontinuity in the experimental pressure wave propagation speed at a void fraction of 50 percent if the entire pressure gradient is assumed to be carried by the liquid for less than 50 percent voids and by the vapor for greater than 50 percent voids; however, the magnitude of the calculated discontinuity is greater than the experimental discontinuity. (auth)
Date: January 1, 1975
Creator: Lyczkowski, R.W.
Partner: UNT Libraries Government Documents Department

Two-phase flow velocity measurement using radiation intensity correlation

Description: Flow velocities of two-phase fluids can be measured by transit time techniques using radiation beams as sensors to detect the passing of inhomogeneities. A Fourier spectrum analysis can be used as a kind of correlation or averaging technique to extract the velocity information from the signal-noise mixture. (auth)
Date: January 1, 1975
Creator: Lassahn, G.D.
Partner: UNT Libraries Government Documents Department

Use of vertical slip flow and flooding models in LOCA analysis

Description: Vertical slip flow and flooding models, which have been incorporated in a version of the RELAP4 computer code by Aerojet Nuclear Company have led to significant improvements in modeling nuclear reactor coolant system phenomena during postulated large and small break loss-of-coolant accidents. The vertical slip flow model computes the separated fluid component velocities and directions at vertical flow junctions. Use of the slip model allows the energy transfer between volumes to be based on individual liquid and vapor component flows rather than on the net junction flow. Continuity and momentum equations are unaffected by the addition of slip. The vertical flow slip model logic is based on the assumption that gravity forces dominate causing slip between phases. 7 references (auth)
Date: January 1, 1975
Creator: Fischer, S.R.
Partner: UNT Libraries Government Documents Department

Fabrication of internally instrumented reactor fuel rods

Description: Procedures are outlined for fabricating internally instrumented reactor fuel rods while maintaining the original quality assurance level of the rods. Instrumented fuel rods described contain fuel centerline thermocouples, ultrasonic thermometers, and pressure tubes for internal rod gas pressure measurements. Descriptions of the thermocouples and ultrasonic thermometers are also contained. (auth)
Date: January 1, 1975
Creator: Schmutz, J.D. & Meservey, R.H.
Partner: UNT Libraries Government Documents Department

FY 1974 program plan for geothermal project

Description: The Program Plan specifies the basic plan for the utilization of FY-74 funds allocated by the AEC Division of Applied Technology and contributions from other participants for the development of geothermal energy in southern Idaho. Funding priorities are dictated by the Construction Data Package submission deadline and the October 1, 1974, site selection. Tasks not funded during FY-74 will be pursued during FY-75. (auth)
Date: February 5, 1974
Partner: UNT Libraries Government Documents Department

Inspection system for Zircaloy clad fuel rods

Description: A description is presented of the design, development, and performance of a remote scanning system for nondestructive examination of fuel rods. Characteristics that are examined include microcracking of fuel rod cladding, fuel-cladding interaction, cladding thickness, fuel rod diameter variation, and fuel rod bowing. Microcracking of both the inner and outer fuel rod surfaces and variations in wall thickness are detected by using a pulsed eddy current technique developed by Argonne National Laboratory (ANL). Fuel rod diameter variation and fuel rod bowing are detected by using two linear variable differential transformers (LVDTs) and a signal conditioning system. The system's mechanical features include variable scanning speeds, a precision indexing system, and a servomechanism to maintain proper probe alignment. Initial results indicate that the system is a very useful mechanism for characterizing irradiated fuel rods. (auth)
Date: October 1, 1975
Creator: Yancey, M.E.; Porter, E.H. & Hansen, H.R.
Partner: UNT Libraries Government Documents Department

One more algorithm for generating elastic and inelastic scattering matrices

Description: Much effort in recent years has been spent on attempts to optimize the numerical problem of calculating elastic and inelastic multigroup scattering matrices from basic ENDF/B data. This paper presents an algorithm which minimizes the amount of data manipulation and approximation required. The algorithm is based on avoiding time-consuming transformations between c.m. and lab coordinates for the differential cross section and the additional requirement with the ETOG algorithm to manufacture Legendre expansion coefficients if tabular distributions are given. The new algorithm was incorporated into the ETOP code, which generates elastic and inelastic scattering matrices for the 68-group Phrog II fast spectrum code. CPU time is roughly a factor of 4 faster than the ETOG algorithm in the most favorable cases for ETOG. (RWR)
Date: January 1, 1975
Creator: Grimesey, R.A.
Partner: UNT Libraries Government Documents Department