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Accurate Nuclear Fuel Burnup Analyses; Eighth Quarterly Progress Report, (September - November 1963)

Description: The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date: December 1, 1963
Creator: Rider, B. F.; Ruiz, C. P.; Luke, P. S., Jr.; Peterson, J. P., Jr. & Smith, F. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Advanced Designs and Special Applications for Fast Breeders

Description: The purpose of this paper is to describe a few of the suggested advanced concepts for fast breeder reactors and to compare these with the standard approach as to their potential advantage. I have attempted to estimate the economic effect of full technical success with each of the proposed concepts. The proposed concepts include: (1) single sodium system, (2) steam-cooled core concept, (3) direct cycle reactor using potassium as reactor coolant and working fluid, (4) molten plutonium-fuel alloy… more
Date: November 11, 1963
Creator: Hammond, R. Philip
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Advanced Test Reactor: Final Shielding Design Report

Description: From abstract: "This report has been prepared as a design reference document describing the calculation methods and engineering results for shielding analysis work done during the design of the Advanced Test Reactor."
Date: December 1963
Creator: Howard, J. O. & Jacks, G. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of UO2 Grain Growth Data From "Out of Pile" Experiments

Description: Summary: Data on equlaxed UO2 grain growth from "out of pile" experiments have been gathered from all known sources and analyzed to determine the relationship between the grain size developed and annealing temperature and between grain size and the time at temperature. On the basis of the analysis, an equation relating gain size to time and temperate has been selected that appears to best describe the data considered as a whole. The coefficients in this grain growth equation have been evaluated… more
Date: November 1963
Creator: Lyons, M. F.; Coplin, D. H. & Weidenbaum, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Application of the Variational Method to the Calculation of the Time Dependence of the Neutron Flux in Small Pulsed Slabs, Cylinders and Spheres

Description: The variational method is applied to the monoenergetic time dependent transport equation to obtain a simple relation for the asymptotic decay constant in small pulsed assemblies. The results indicate that flat trial functions may be a reasonable representation of the flux distributions in the thin slab limit. This approach is superior to many of the usual transport approximations.
Date: December 16, 1963
Creator: Judge, F. D. & Daitch, Paul B. (Paul Bernard), 1925-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Applications of Strain Cycling Considerations to Superheat Fuel Design

Description: A potential performance limitation of superheat fuel is the susceptibility of the fuel cladding to low cycle fatigue failure. Two simplified analytical methods are presented to estimate the cyclic lifetime of circular superheat fuel cladding. One failure relation is based on a displacement method. The other failure relation is based on a stress method. These relations were compared with data from the literature, and with data involving damage obtained by Reynolds. A recommended design procedur… more
Date: June 1963
Creator: Rieger, G. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Approximate Models for Distributed-Parameter Heat-Transfer Systems

Description: Summary: The use of dimensionless-parameter frequency response diagrams to determine accuracies of lumped-parameter approximations is demonstrated by two examples: calculation of the heat flux at the surface of a semi-infinite solid due to temperature fluctuations of an adjacent fluid; and the response of a counterflow heat exchanger to inlet fluid temperature perturbations. Dimensionless system parameters make it possible to use general-purpose plots to find the error in particular approxima… more
Date: August 20, 1963
Creator: Ball, S. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Asymptotic Neutron Spectra in Multiplying Media

Description: Asymptotic low energy neutron spectra have been measured for two multiplying systems. The reentrant hold spectrum (scalar flux) and the surface leakage spectrum were obtained for both assemblies using the pulsed-source chopper technique at the RPI linear accelerator.
Date: November 1963
Creator: Slovacek, R. E.; Fullwood, R. R.; Gaerttner, Erwin Rudolf, 1911- & Bach, D. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Atomic Energy Commission - Bureau of Mines Process Heat Reactor Program: Quarterly Progress Report [for] August 1 to October 31, 1962

Description: Quarterly report discussing a Atomic Energy Commission - Bureau of Mines program on the use of nuclear heat for coal gasification and chemical processing.
Date: 1963~
Creator: Coates, N. H.; Abel, W. T.; Gall, R. L.; McGee, J. P. & Hirst, L. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Atomic Energy Commission - Bureau of Mines Process Heat Reactor Program: Quarterly Progress Report [for] February 1 to April 30, 1962

Description: Quarterly report discussing a Atomic Energy Commission - Bureau of Mines program on the use of nuclear heat for coal gasification and chemical processing.
Date: 1963~
Creator: Coates, N. H.; Abel, W. T.; Gall, R. L.; Hirst, L. L.; McGee, J. P. & Shale, C. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Atomic Energy Commission-Bureau of Mines Process Heat Reactor Program: Quarterly Progress Report [for] May 1 to July 31, 1962

Description: Quarterly report discussing a Atomic Energy Commission - Bureau of Mines program on the use of nuclear heat for coal gasification and chemical processing.
Date: 1963~
Creator: Coates, N. H.; Abel, W. T.; Gall, R. L.; Shale, C. C.; McGee, J. P. & Hirst, L. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Atomic Energy Commission - Bureau of Mines Process Heat Reactor Program: Quarterly Progress Report [for] November 1, 1961 to January 31, 1962

Description: Quarterly report discussing a Atomic Energy Commission - Bureau of Mines program on the use of nuclear heat for coal gasification and chemical processing.
Date: 1963~
Creator: Coates, N. H.; Abel, W. T.; Shale, C. C.; McGee, J. P. & Hirst, L. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Atomic Energy Commission - Bureau of Mines Process Heat Reactor Program: Quarterly Progress Report [for] November 1, 1962 to January 31, 1963

Description: Quarterly report discussing a Atomic Energy Commission - Bureau of Mines program on the use of nuclear heat for coal gasification and chemical processing.
Date: 1963~
Creator: Coates, N. H.; Abel, W. T.; Gall, R. L.; Gibson, H. G.; McGee, J. P. & Hirst, L. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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