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Transient three-dimensional thermal-hydraulic analysis of nuclear reactor fuel rod arrays: general equations and numerical scheme

Description: A mathematical model and a numerical solution scheme for thermal- hydraulic analysis of fuel rod arrays are given. The model alleviates the two major deficiencies associated with existing rod array analysis models, that of a correct transverse momentum equation and the capability of handling reversing and circulatory flows. Possible applications of the model include steady state and transient subchannel calculations as well as analysis of flows in heat exchangers, other engineering equipment, and porous media. (auth)
Date: November 1, 1975
Creator: Wnek, W.J.; Ramshaw, J.D.; Trapp, J.A.; Hughes, E.D. & Solbrig, C.W.
Partner: UNT Libraries Government Documents Department

Evaluation of the effects of an integral fin spacer design on predicted fuel pin and subassembly duct performance

Description: The effect of an integrally finned fuel pin cladding design on LMFBR subassembly performance has been evaluated. Effects on thermal/hydraulics, fuel pin lifetime and duct lifetime are considered. Results are presented for 19, 61 and 217 pin subassemblies.
Date: January 1, 1976
Creator: Sutherland, W.H.; Cantley, D.A.; McCurry, D.C. & Parker, M.B.
Partner: UNT Libraries Government Documents Department

Maximim Accelerations On The Fuel Assemblies Of a 21-PWR Waste Package During End Impacts

Description: The objective of this calculation is to determine the acceleration of the fuel assemblies contained in a 21-Pressurized Water Reactor (PWR) spent nuclear fuel waste package impacting an unyielding surface. A range of initial velocities of the waste package is studied. The scope of this calculation is limited to estimating the acceleration of the fuel assemblies during the impact.
Date: March 27, 2003
Creator: Brosse, V. DeLa
Partner: UNT Libraries Government Documents Department

Maximim Accelerations On The Fuel Assemblies Of a 21-PWR Waste Package During End Impacts

Description: The objective of this calculation is to determine the acceleration of the fuel assemblies contained in a 21-Pressurized Water Reactor (PWR) spent nuclear fuel waste package impacting an unyielding surface. A range of initial velocities of the waste package is studied. The scope of this calculation is limited to estimating the acceleration of the fuel assemblies during the impact.
Date: August 17, 2005
Creator: Schmitt, T.
Partner: UNT Libraries Government Documents Department

Isochoric Implosions for Fast Ignition

Description: Various gain models have shown the potentially great advantages of Fast Ignition (FI) Inertial Confinement Fusion (ICF) over its conventional hot spot ignition counterpart [e.g., S. Atzeni, Phys. Plasmas 6, 3316 (1999); M. Tabak et al., Fusion Sci. & Technology 49, 254 (2006)]. These gain models, however, all assume nearly uniform-density fuel assemblies. In contrast, conventional ICF implosions yield hollowed fuel assemblies with a high-density shell of fuel surrounding a low-density, high-pressure hot spot. Hence, to realize fully the advantages of FI, an alternative implosion design must be found which yields nearly isochoric fuel assemblies without substantial hot spots. Here, it is shown that a self-similar spherical implosion of the type originally studied by Guderley [Luftfahrtforschung 19, 302 (1942)] may be employed to yield precisely such quasi-isochoric imploded states. The difficulty remains, however, of accessing these self-similarly imploding configurations from initial conditions representing an actual ICF target, namely a uniform, solid-density shell at rest. Furthermore, these specialized implosions must be realized for practicable drive parameters and at the scales and energies of interest in ICF. A direct-drive implosion scheme is presented which meets all of these requirements and reaches a nearly isochoric assembled density of 300 g=cm{sup 3} and areal density of 2.4 g=cm{sup 2} using 485 kJ of laser energy.
Date: April 4, 2007
Creator: Clark, D S & Tabak, M
Partner: UNT Libraries Government Documents Department

209-E Building -- Response to ventilation failure evaluation

Description: This document provides an evaluation and recommendations for radiological workplace air monitoring and response to ventilation failure for the Critical Mass Laboratory, 209-E Building. The Critical Mass Laboratory, part of the 209-E Building, was designed to provide a heavily shielded room where plutonium and uranium liquid solutions could be brought into various critical configurations under readily controlled and monitored conditions. The facility is contained within a one-story L-shaped concrete block and reinforced concrete building. One wing houses offices, a control room, shops, and a common area while the other wing includes an equipment room, the change room, work areas, and the two-story Critical Assembly Room (CAR). Three of the rooms contain radiologically contaminated equipment and materials.
Date: July 27, 1998
Creator: Foust, D.J.
Partner: UNT Libraries Government Documents Department

Shippingport Spent Fuel Canister (SSFC) Design Report Project W-518

Description: The SSFC Design Report Describes A spent fuel canister for Shippingport Core 2 blanket fuel assemblies. The design of the SSFC is a minor modification of the MCO. The modification is limited to the Shield Plug which remains unchanged with regard to interfaces with the canister shell. The performance characteristics remain those for the MCO, which bounds the payload of the SSFC.
Date: January 27, 2000
Creator: JOHNSON, D.M.
Partner: UNT Libraries Government Documents Department

Decay heat fractions for DFA 8213 and 4192

Description: Decay heat fractions for FFTF driver fuel assemblies 8213 and 4192 were calculated to allow the assembly nozzles to be cut. Cutting the nozzles is required to allow the assemblies to fit in the center location of a core component container in an Interim Storage Cask.
Date: February 6, 1997
Creator: Kessler, S.F., Fluor Daniel Hanford
Partner: UNT Libraries Government Documents Department

Improved MK42 Melting Model

Description: An improved Mark 42 melting model has been defined for establishing confinement protection limits (CPLs). This report describes the new melting model and its application in computing CPLs.
Date: September 19, 2001
Creator: Tudor, A.A.
Partner: UNT Libraries Government Documents Department

Mark 22 Reactivity

Description: Calculations for reactivity held in control rods have underpredicted the observed Mark 22 reactivity. Reactivity predictions by charge designers have accounted for this by including large biases which change with exposure and reactor region. The purpose of this study was to thoroughly investigate the methods and data used in the reactivity calculations. The goal was to identify errors and improvements and make necessary corrections.
Date: July 2, 2001
Creator: Buckner, M.R.
Partner: UNT Libraries Government Documents Department

Uncertainties Affecting BOSFN for the Mark 15 Assembly

Description: Technical and transient protection limits are specified on the nominal burnout safety factor, BOSFN, to avoid significant release of fission products caused by local film boiling burnout. The risk of fission product release, BOR, due to film boiling burnout is statistically determined where allowances are made to account for differences between the nominal assembly and the actual assembly. This report describes the calculational model behind BOR and how the specific numerical values were estimated. The data listed in this report enable damage calculations with COBAD to be performed for the Mark 15 assembly.
Date: August 9, 2001
Creator: Hamm, L.L.
Partner: UNT Libraries Government Documents Department