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Anticipated heat generation rate of MGCR-III fuel element as a function of enrichment

Description: The DR-1 Loop, located in the C test hole of the DR Reactor, provides a high temperature, recirculating gas-cooled facility for the irradiation of experimental fuel elements. The loop is being utilized currently by General Atomic, a Division of General Dynamics, to evaluate fuel elements in support of their work on the Maritime Gas-Cooled Reactor Program, a program which is directed at the development of a ship propulsion unit consisting of a gas-cooled reactor driving a closed cycle gas turbin… more
Date: June 2, 1960
Creator: Bunch, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Application of an Operational Reactivity Accounting System Based on One-Group Diffusion Theory

Description: HW-70780, {open_quotes}An Operational Reactivity Accounting System Based on One-Group Diffusion Theory{close_quotes} describes a reactivity accounting system which is an improvement over the present {open_quotes}flux-squared weighting{close_quotes} system. Several changes and additions have been made which will simplify and increase the accuracy of the system described in the parent document. The changes occur primarily in the application of the system and are compatible with diffusion theory a… more
Date: July 2, 1962
Creator: Stewart, S. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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BIO-ORGANIC CHEMISTRY QUARTERLY REPORT. June through August1963

Description: This report covers the following titles: (1) The Effects of 8-Methyl Lipoic Acid on the Evolution of Oxygen and Reduction of Carbon Dioxide during Photosynthesis; (2) Further {sup 14}C and {sup 15}N Tracer Studies of Amino Acid Synthesis during Photosynthesis by Chlorella Pyrenoidosa; (3) Two-Dimensional High Voltage, Low-Temperature Paper Electrophoresis of {sup 14}C-Labeled Products of Photosynthesis with {sup 14}CO{sub 2}; (4) A Search for Enzymic and Nonenzymic Reactions Between Thiamine De… more
Date: October 2, 1963
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Calculations of the surface heat flux and fuel temperatures for PRTR MK-I PuO{sub 2}-UO{sub 2} fuel element with segregated PuO{sub 2}

Description: The methods used to fabricate the present loading of PuO{sub 2}-UO{sub 2} fuel elements for the Plutonium Recycle Test Reactor have resulted in alternating bands of high and low PuO{sub 2} concentration along each rod of the 19-rod elements. These bands are repeated every 1/2 or 1 inch along the length of the rod, depending on whether the loading of the oxides was done in 160 or 80 increments. This non-uniform distribution of PuO{sub 2} results in alternate regions of high and low heat generati… more
Date: January 2, 1963
Creator: Zaloudek, F. R. & Hesson, G. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Capillary liquid evaporation from wick covered plates: theory

Description: Differential equations and associated parameters are derived for heat transfer to a thin liquid-saturated wick, as in the evaporator section of a ''heat pipe.'' Prescribed are a numerical method of solution and a procedure for experimental measurements of heat transfer in the flat plate model. This effort is a part of the Project CLEER program which is currently sponsored by the Mechanical Engineering Department research account.
Date: June 2, 1969
Creator: Van Sant, J. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Comment on Temperature-Pressure Equilibrium Between Dispersed and Continuous Phases of a Material

Description: This memo calls attention to the fact that the relationship between equilibrium temperature and the pressures in two phases of a material is {Delta}sdT = {Delta}(vdP) , and not, as now routinely assumed by bubble investigators, the Clausius-Clapeyron equation {Delta}sdT = {Delta}vdP . If one phase is discontinuous (subscript "d") and consists of spheres of radius r in a continuous phase (subscript "c") whose pressure is held constant, then the equilibrium temperature will be… more
Date: September 2, 1969
Creator: Lyon, R. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Computer Program for Calculating One-Dimensional Hydrodynamic Flow: KO Code

Description: A computer program is described for the solution of shock, detonation, and spall problems for one-dimensional linear, cylindrical, or spherical hydrodynamic flow. The Flume option is used for calculating flow- through arbitrary cross sections. (R.J.S.)
Date: July 2, 1962
Creator: Wilkins, M.; French, J. & Giroux, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Contraction of graphite: A comparison of laboratory and production reactor data, Part 2, KE and KW Reactors

Description: Part 1 of this two-part report presented a comparison of the irradiation-induced contraction rates obtained on standard-size graphite samples and the apparent moderator contraction rates of H, DR and C Reactors. The distortion trends of the top center of the graphite stacks, from which the apparent moderator contraction rates were derived, were presented as a function of cumulative power generation since start-up for each of the six older Hanford reactors. Since KE and KW Reactors are of identi… more
Date: January 2, 1963
Creator: Giberson, R. C. & Morgan, W. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Conversion ratio tables

Description: This manual provides a list of the quantities of plutonium and plutonium isotope formation. Other isotopes whose concentrations are important and included in this report are U-236 buildup, U-235 burnout, U burnout, Np-237 build-up, GVR (the Gas Volume Ratio) in coproduct target elements and equivalent gram of plutonium. These conversion tables have been calculated on the IBM 7090 digital computer using a program entitled ``FLEX-3.`` The results of the computer solutions have not been normalized… more
Date: July 2, 1965
Creator: Chitwood, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Cover sheet for a Hanford Historial Document for public availability

Description: The following criteria defines the objectives, bases and functional requirements that shall govern the preparation of the final design for the zirconium process tube installation program at the 100-K Areas. As a result of this program, reduced operating costs and increased production can be achieved. The present central zone aluminum tubes in the 100-K Reactors require replacement every to to three years to prevent excessive failures resulting from the thinning of the tube walls by corrosion. R… more
Date: August 2, 1962
Creator: Schack, M. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Distribution of time between unscheduled outages

Description: A study is in progress in which reactor operations will be simulated on the computer, the primary purpose being to evaluate the costs associated with various administrative alternatives which may be followed in conducting the overall operation, in addition to defining how operational costs are affected by such things as changes in fuel quality. The problem is complicated by the fact that the operation of the reactors is largely affected by random occurrences; no one can predict exactly when a t… more
Date: January 2, 1963
Creator: Jaech, J. L. & Burke, R. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Effect of increased nickel content in canning baths

Description: Canning bath Al-Si, supplied from offsite vendors and reclaimed lathe turnings in the 313 building, is used in the production of I & E fuel elements. A study was made of the effect of increasing the Ni content to over 0.5% in the canning baths, in order that all of the X-8001 scrap could be reclaimed. Effect on bond quality, weld integrity, and canning bath operation was studied. Based on adverse weld quality, slight loss in reactivity, and potential for furnace channel plugging, it is recommen… more
Date: February 2, 1960
Creator: Strand, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fabrication of enriched hot die sized diffusion bonded fuel elements for Production Test IP-616-A

Description: Hot die sizing (HDS) is a process being investigated to replace the existing AlSi brazing process. Hot die sizing consists of sizing a nickel-plated core and aluminum can assembly with cold dies to produce a diffusion bonded aluminum clad fuel element. Upon completion of fabrication of the first natural uranium hot die sized fuel elements for production test IP-546-A, the next step in evaluation of the process was to assemble enriched fuel for further irradiation testing. This report summarizes… more
Date: October 2, 1964
Creator: Strand, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hanford toll irradiation study

Description: This report presents details of the Hanford toll irradiation study. The objective of the study was to provide a basis for establishing charges for irradiation of neptunium for private parties on a toll basis.
Date: September 2, 1969
Creator: Woods, W.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Helios pulsed nuclear propulsion concept

Description: A Helios-propelled vehicle would make use of a containment vessel--perhaps 30 feet in diameter--in which small nuclear explosive charges would be placed, together with a few hundred pounds of hydrogen. Firing of a charge would result in bringing the mixture of charge residue and hydrogen to a high temperature--say 5000 or 6000/sup 0/K--and subsequent release through a nozzle would provide propulsive thrust. This process would be repeated several thousand times, at intervals likely to be 10 seco… more
Date: June 2, 1965
Creator: Hadley, J. W.; Stubbs, T. F.; Janssen, M. A. & Simons, L. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

IPD reactor training text, declassified supplement: Chapter 2, Design and construction of the Hanford production reactors

Description: Purpose of this chapter is to provide an overview of reactor construction and an understanding of important design considerations: how it is built, why it was built that way, what it is supposed to do, what the nuclear safety considerations are, and what one needs to know about its design/construction to properly operate it.
Date: July 2, 1963
Creator: Wade, G. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Laboratory determination of normal operating flow rates with enlarged outlet fittings -- BDF reactors

Description: Experiments have been conducted in the Hydraulics Laboratory, at the request of IPD`s Mechanical Development-A Operation, to determine the energy losses of various enlarged outlet fitting combinations. These experiments were conducted an steady state runs and allow the determination of the normal operating point (flow rate) of a reactor process channel under selected conditions of front header pressure and fuel charge. No attempt is made to make a mechanical or economic evaluation of the partic… more
Date: February 2, 1960
Creator: Waters, E. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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