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Fuel Element Development Program for the Pebble Bed Reactor

Description: Previous results from the Pebble Bed Reactor Fuel Element Development Program had shown the excellent promise of vapor-deposited Al2O3 doq5intw on UO2 particles as a low permeability high temperature fission product barrier. However, since the matrix material for the PBR fuel element is a graphite sphere, carbonaceous coatings on the dispersed fuel particles might be of more interest because of improved particle coating-matrix compatibility and no displacement of neutron moderating materials. … more
Date: 1961
Creator: Sanderson & Porter, Inc.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Cost of Steam Supply for Desalting Using Coal Fired Boilers

Description: Report studying the application and cost of using coal based steam power plants in desalination plants. Both Single Purpose Plants (wherein power is produced for the plant's needs) and Dual Purpose Plants (wherein extra power is produced for sale) are investigated.
Date: December 1970
Creator: Sichel, Peter & Nagelberg, George
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Element Development Program for the Pebble Bed Reactor

Description: ...Development during this quarter have caused a shift in emphasis of the Pebble Bed Reactor Fuel Element Development Program from coatings on the sphere surface to coatings on individual fuel particles as the major deterrent to fission product leakage. In a high level irradiation test, cracks developed in the coatings of specimens coated with pyrolytic carbon and siliconized silicon carbide. In another high level irradiation test, a graphite sphere fueled with Al2O3 coated with UO2 particles … more
Date: 1960
Creator: Sanderson & Porter, Inc.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Coolball, a Machine Code for Thermal Analysis of Pebble Bed Reactor Cores

Description: COOLBALL is an IBM 650 machine program designed to calculate local gas and ball temperatures, gas flow, and pressure loses as induced by non-uniform power generation and voidage within an axial flow Pebble Bed Reactor core. This code has been used extensively to study the thermal characteristics of Pebble Bed Reactor cores in support of a broad program for the development of the PBR concept.
Date: [1961]
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fuel Element Development Program for the Pebble Bed Reactor

Description: A variety of spherical uranium-graphite fuel elements were fabricated with the objective of meeting the requirements of the Pebble Bed Reactor. Major emphasis was on silicon-silicon carbide coatings, pyrolytic carbon coatings and alumina coated fuel particles. An exploratory program on the limits of thorium oxide loadings by the infiltration process was started.Poor results with sintered alumina coated UO2 particles led to development work on alumina coating by vapor deposition for which the … more
Date: 1960
Creator: Sanderson & Porter, Inc.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PBM, A Two-Group, Two-Region Reactor Model for Homogeneous, Highly Absorbing Systems and Machine Codes for Its Application

Description: A nuclear model has been developed for homogeneous, two-region reactors possessing a relatively large percentage of epithermal absorption in both the core and blanket region. A number of new IBM 650 programs have been developed and existing programs modified to form a group of programs, compatible with the nuclear model and with each other, which can be used for preliminary evaluation of the effed of design variable on reactor characteristics.
Date: December 1960
Creator: Sanderson & Porter, Inc.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Pebble Bed Reactor Program

Description: Several different types of experimental facilities have been evaluated to determine the most suitable and economical means of demonstrating the technical feasibility of the Pebble Bed Reactor concept. The criteria for demonstrating technical feasibility are: 1) bulk irradiation of fuel elements in order to obtain statistical data on performance, 2) Maintenance of system activity at specified levels, and 3) Feasible maintenance procedures. An additional criterion, which is required to achieve b… more
Date: 1959
Creator: Sanderson & Porter, Inc
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Pebble Bed Reactor Program

Description: The coolant stream of all nuclear reactors caries some activity due to one or more of the following: a) neutron activation of coolant atoms, b) neutron activation of corrosion products carried by the coolant stream, c) fission recoil into the coolant stream, d) fission products leaking into the coolant stream. The Pebble Bed Reactor is not concerned with (1) and (b) since the helium working fluid, or coolant, has an activation cross-section which is essentially zero and its inert chemical natu… more
Date: 1960
Creator: Sanderson & Porter, Inc.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Pebble Bed Friction Factor and Thermal Expansion Tests

Description: Tests were conducted to determine the friction factor of randomly packed beds of 3/4-inch diameter spheres in 8-inch and 15-1/4-inch diameter beds, and of 1-1/2-inch diameter spheres in 15-1/4-inch diameter bed. The bed depths were varied in an attempt to isolate the effects of entrance and exit losses. The bed Reynolds number, base on sphere diameter, was varied from 5,000 to 50,000.
Date: August 31, 1960
Creator: Leeman, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design and Feasibility Study of a Pebble Bed Reactor-Steam Power Plant

Description: Originally issued as S and P 1963A, Parts I and II. This report covers a design and feasibility study of a pebble bed reactor-steam power plant of 125 megawatt electrical output. The reactor design which evolved from this study is a two-region thermal breeder, operating on the uranium-thorium cycle, in which all core structural materials are graphite. Fuel is in the form of unclad spherical elements of graphite, containing fissile and fertile material. The primary loop consists of the reactor … more
Date: May 1, 1958
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Adsorption of Radioactive Gases on Activated Carbon

Description: The purpose of this experiment is to study the quantitative adsorption characteristics of a carbon adsorber bed receiving a radioactive inert gas in a helium stream. An objective of the experiment is to measure the equilibrium transmission of the radio-active gas through a carbon adsorber in order to determine if radio-active decay of the adsorbed gas permits additional adsorption.
Date: August 31, 1960
Creator: Madey, Richard; Barker, J. J.; Beebe, M. R. & Stephenson, T. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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