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MIT LMFBR blanket physics project progress report No. 7, July 1, 1975--September 30, 1976

Description: Work during the period was devoted primarily to a range of analytical/numerical investigations, including evaluation of means to improve external blanket designs, beneficial attributes of the use of internal blankets, improved methods for the calculation of heterogeneous self-shielding and parametric studies of calculated spectral indices. Experimental work included measurements of the ratio of U-238 captures to U-235 fissions in a standard blanket mockup, and completion of development work on … more
Date: September 30, 1976
Creator: Driscoll, M.J. (ed.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Cross-section sensitivity analyses for a Tokamak Experimental Power Reactor

Description: The objectives of this report were (1) to determine the sensitivity of neutronic responses in the preliminary design of the Tokamak Experimental Power Reactor by Argonne National Laboratory, and (2) to develop the use of a neutron-gamma coupled cross-section set in the calculation of cross-section sensitivity analysis. Response functions such as neutron plus gamma kerma, Mylar dose, copper transmutation, copper dpa, and activation of the toroidal field coil dewar were investigated. Calculations… more
Date: September 1, 1977
Creator: Simmons, E.L.; Gerstl, S.A.W. & Dudziak, D.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermal problems on high flux beam lines

Description: Wiggler and undulator magnets can provide very intense photon flux densities to beam line components. This paper addresses some thermal/materials consequences due to such impingement. The LBL/Exxon/SSRL hybrid-wiggler Beam Line VI now nearing operation will be able to provide up to approx. 7 kW of total photon power at planned SPEAR operating conditions. The first masks are located at 6.5 meters from the source and may receive a peak power density (transverse to the beam) exceeding 20 kW/cm/sup… more
Date: September 1, 1983
Creator: Avery, R.T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Engineering analysis of TFTR disruption

Description: This report covers an engineering approach quantifying the currents, forces, and times, as well as plasma position, for the worst-case disruption based on engineerign circuit assumptions for the plasma. As the plasma moves toward the wall during the current-decay phase of disruption, the wall currents affect the rate of movement and, hence, the decay time. The calculated structure-induced currents differ considerably from those calculated using a presently available criterion, which specifies t… more
Date: September 1, 1984
Creator: Murray, J. G.; Rothe, K. E. & Bronner, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Gamma heating measurements in a mixed radiation field

Description: Gamma hearing measurements have been made in a low-Z assembly irradiated with 14-MeV neutrons and (n,n{prime}) gammas produced by a Texas Nuclear Model 9400 neutron generator. The assembly is composed of 144 magnesium sleeves (5cm {times} 5cm {times} 60cm {times} 3 mm thick) filled with graphite to simulate a fusion blanket test module. Heating measurements were made in the mid-line of the assembly using a proportional counter operating in the Continuously-varied Bias-voltage Acquisition (CBA) … more
Date: September 1, 1990
Creator: Chiu, H.K. (Illinois Univ., Urbana, IL (USA). Dept. of Nuclear Engineering); Bennett, E.F. & Micklich, B.J. (Argonne National Lab., IL (USA))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Heat transfer at a beam port corner

Description: Along the general run of the vacuum chamber synchrotron radiation strikes the wall at a glancing angle of about 5.6/sup 0/. The heat source is well-approximated by a ribbon of uniform power density having a small vertical height and an infinite azimuthal length. The heat transfer problem reduces to one in two-dimensions and it has been considered in a previous note. At the corner of a beam port the angle of incidence becomes 90/sup 0/, so the temperature rises much higher than elsewhere. Since … more
Date: September 8, 1978
Creator: Krinsky, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Decay heat of /sup 235/U fission products by beta- and gamma-ray spectrometry

Description: The fast-rabbit facilities of the ORRR were used to irradiate 1- to 10-..mu..g samples of /sup 235/U for 1, 10, and 100 s. Released power is observed using nuclear spectroscopy to permit separate observations of emitted ..beta.. and ..gamma.. spectra in successive time intervals. The spectra were integrated over energy to obtain total decay heat and the ..beta..- and ..gamma..-ray results are summed together. 10 fig, 2 tables. (DLC)
Date: September 1, 1976
Creator: Dickens, J. K.; Love, T. A.; McConnell, J. W. & Peelle, R. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Heat generation in stored Redox wastes

Description: Fission product activities and heat generated by fission product decay as a function of time, in waste solutions obtained by processing uranium irradiated under the present Hanford schedule, were calculated. From these data, curves showing expected heat evolution in stored Redox Process Wastes, during and following filling of the waste tanks, were prepared assuming various modes of operating the plant and various production rates. Total heat available for evaporation of water from the tanks was… more
Date: September 2, 1952
Creator: Kane, J. S. & Burns, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary radiation criteria and nuclear analysis for ETF

Description: Preliminary biological and materials radiation dose criteria for the Engineering Test Facility are described and tabulated. In keeping with the ETF Mission Statement, a key biological dose criterion is a 24-hour shutdown dose rate of 2 mrem/hr on the surface of the outboard bulk shield. Materials dose criteria, which primarily govern the inboard shield design, include 10/sup 9/ rads exposure limit to epoxy insulation, 3 x 10/sup -4/ dpa damage to the TF coil copper stabilizer, and a total nucle… more
Date: September 1980
Creator: Engholm, B. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Wavefront sensors for optical diagnostics in fluid mechanics: Application to heated flow, turbulence and droplet evaporation

Description: Optical measurement techniques are extremely useful in fluid mechanics because of their non-invasive nature. However, it is often difficult to separate measurement effects due to pressure, temperature and density in real flows. Using a variation of a Shack-Hartmann wavefront sensor, we have made density measurements that have extremely large dynamic range coupled with excellent sensitivity at high temporal and spatial resolution. We have examined several classes of flow including volumetrically… more
Date: September 1, 1993
Creator: Neal, D. R.; O`Hern, T. J.; Torczynski, J. R.; Warren, M. E.; Shul, R. & McKechnie, T. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Minimization of the effect of errors in approximate radiation view factors

Description: The maximum temperature of irradiated fuel rods in storage containers was investigated taking credit only for radiation heat transfer. Estimating view factors is often easy but in many references the emphasis is placed on calculating the quadruple integrals exactly. Selecting different view factors in the view factor matrix as independent, yield somewhat different view factor matrices. In this study ten to twenty percent error in view factors produced small errors in the temperature which are w… more
Date: September 1, 1993
Creator: Clarksean, R. & Solbrig, C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Models and correlations of the DEBRIS Late-Phase Melt Progression Model

Description: The DEBRIS Late Phase Melt Progression Model is an assembly of models, embodied in a computer code, which is designed to treat late-phase melt progression in dry rubble (or debris) regions that can form as a consequence of a severe core uncover accident in a commercial light water nuclear reactor. The approach is fully two-dimensional, and incorporates a porous medium modeling framework together with conservation and constitutive relationships to simulate the time-dependent evolution of such re… more
Date: September 1, 1997
Creator: Schmidt, R.C. & Gasser, R.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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