200 area weekly report (open access)

200 area weekly report

None
Date: April 14, 1955
Creator: Christl, R. J.
Object Type: Report
System: The UNT Digital Library
300 Area ``X`` Program, Basis ``B`` (open access)

300 Area ``X`` Program, Basis ``B``

Attached is a secret draft of 300 Area expansion for the proposed ``X`` Program (600 MWD level for indefinite period) made up of the following: (1) assumptions; (2) present facilities and to what extent inadequate; (3) description of proposed work; (4) advantages to be gained and justification for proposed work; (5) why existing or alternate facilities cannot be used; (6) estimate of cost; and (7) attachments.
Date: March 14, 1952
Creator: Wood, V. W.
Object Type: Report
System: The UNT Digital Library
Analysis of a standard Pu solution by the control laboratories in 231 and 234-5 Buildings (open access)

Analysis of a standard Pu solution by the control laboratories in 231 and 234-5 Buildings

A solution of Pu was prepared for use in a re-investigation of the present 49 titration method. Three 500 microliter portions of the sample were dried and ignited to PuO{sub 2}. From the weight of the residue and the impurity analysis, the concentration, in g/l, of the solution was found to be 222.2, 221.5, and 222.5; average of 222.0. The six samples submitted to the control laboratory in Bldg. 231 were reported as: 219.3, 223.6, 221.5, 220.9, 222.3, and 228.2 (re-run 229.3); average of 222.6 g/l. The 234-5 Laboratory reported: 228.2, 233.3, 220.2, 236.1, 225.2 (re-run 220.6), and 227.9; average of 227.3 g/l. Since the standardization was carried out on April 13, the 231 Lab received its samples on May 11, and the 234-5 Lab received their samples on May 23, a correction for increase in concentration due to decomposition of the water by alpha particles and evaporation was calculated. It was determined that the results reported by the 231 Lab were very consistent (except for one determination) and that the average value agreed with the gravimetric determination. The average results from the 234-5 Lab are 2% higher than the gravimetric results. Further studies are being made on the chemical …
Date: July 14, 1950
Creator: Barton, G.B.
Object Type: Report
System: The UNT Digital Library
Application of a Modified Debye-Huckel Theory to Fully Ionized Gases (open access)

Application of a Modified Debye-Huckel Theory to Fully Ionized Gases

The equations of the Debye-Huckel theory, modified to include quantum statistics, are discussed. It is found that the nonlinear equations used by Cowan and Kirkwcod are not unique and that the nonlinear theory can be formulated in different ways to give different answers. The linearized equations of these alternative formulations are discussed, and the correct form of the linearized theory is established. From the linear theory, the Helmholtz free energy of a slightly degenerate plasma is derived, and from this result, useful formulas in the near-classical limit are obtained for the pressure and internal energy. (auth)
Date: August 14, 1959
Creator: Kidder, R. E. & DeWitt, H. E.
Object Type: Report
System: The UNT Digital Library
Application of neutron monitors to process control in Recuplex. Status report (open access)

Application of neutron monitors to process control in Recuplex. Status report

A program was. initiated early in 1957 to develop a neutron monitor capable of detecting plutonium (Pu) concentration in process vessels in Recuplex. This followed an earlier application by Finished Products Operation and Research and Engineering of neutron monitoring to powder counting which had been successful and was being regularly used. The process vessel monitoring was to be done by the ``in tank probe`` method, utilizing the monitored solution as its own-moderator, and detecting the resulting slow and thermal neutrons with boron trifluoride (BF{sub 3}) type proportional counters. This report is intended to present the history of the Recuplex program; a summary of the development work to date; the current status of the monitoring system; and the immediate plans for future installations and work. This report is intended as a design guide for presently scheduled and future monitor installations in Recuplex and elsewhere of the types herein described. The report also includes calibration curves for both D-11 tank and H-3 column monitors, schematic representation of all installations, manual switching panel circuit diagram, pre-amplifier circuit diagram, probe well designs, and Kl-2 instrument tank design.
Date: July 14, 1958
Creator: Kelly, P. R. & Hildreth, N. T.
Object Type: Report
System: The UNT Digital Library
Aqueous Corrosion of Uranium and Alloys: Survey of Project Literature (open access)

Aqueous Corrosion of Uranium and Alloys: Survey of Project Literature

None
Date: May 14, 1952
Creator: McWhirter, J. W. & Draley, J. E.
Object Type: Report
System: The UNT Digital Library
Authorization for process change 234-5 Building (open access)

Authorization for process change 234-5 Building

None
Date: March 14, 1952
Creator: Mobley, W.N. & Cooper, V.R.
Object Type: Report
System: The UNT Digital Library
A Bibliography of Available Digital Computer Codes for Nuclear Reactor Problems (open access)

A Bibliography of Available Digital Computer Codes for Nuclear Reactor Problems

This bibliography provides a ready listing of reactor digital computer codes presently available or in preparation, and is arranged in such a manner as to enable the engineer or physicist to determine which codes will be of assistance to him in his work.
Date: October 14, 1955
Creator: Radkowsky, A. & Brodsky, R.
Object Type: Report
System: The UNT Digital Library
BLANKET DUMP TANKS AND CONDENSATE TANKS. HRT Engineering Test Procedures No. IV 34a, b, c, and 37 (open access)

BLANKET DUMP TANKS AND CONDENSATE TANKS. HRT Engineering Test Procedures No. IV 34a, b, c, and 37

None
Date: April 14, 1956
Creator: Burch, W.D.
Object Type: Report
System: The UNT Digital Library
Charge-discharge during pile operation (open access)

Charge-discharge during pile operation

This document presents a general analysis of charge-discharge during pile operation. It is not a detailed technical, operational, economic, or political analysis but, rather an attempt to cover the subject with a broader viewpoint than is usually prsented in the many detailed reports which have been written in the past five years. This letter is occasioned at this time because efforts are in progress to implement plans for proceeding with the expenditure of substantial amounts of money in order to demonstrate that the system, as developed, will allow the attainment of certain desirable objectives.
Date: April 14, 1955
Creator: Lovington, R. C.
Object Type: Report
System: The UNT Digital Library
Chemical Development Status Report for Week Ending June 8, 1956 (open access)

Chemical Development Status Report for Week Ending June 8, 1956

This report talks about Chemical Development Status Report for Week Ending June 8, 1956
Date: June 14, 1956
Creator: Blanco, R. E. & Ferguson, D. E.
Object Type: Report
System: The UNT Digital Library
CHEMISTRY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING JUNE 20, 1959 (open access)

CHEMISTRY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING JUNE 20, 1959

The H-F conductance and susceptance were determined for coil-type vessels over a range of frequencies from 2 to 30 mc. The ultraviolet absorption spectra of organic compounds in the vapor phase were determined, and a maximum was assigned to each compound. The dielectric constant values for five alpha substituted ketones at 25 deg C are reponted. A series of acids in dimethylformamide was titrated with the alkali methoxides by the high-frequency and conductance methods. The titration curves by these two methods were very similar in shape and also very similar to the curves for the corresponding type of acid in aqueous solution (W.L.H.)
Date: September 14, 1959
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Comments on the Angle of Repose of Aqueous ThO$sub 2$ Slurries (open access)

Comments on the Angle of Repose of Aqueous ThO$sub 2$ Slurries

aqueous thorium oxide slurries have arisen in connection with the design of the lower portion of the blanket pressure vessel and its associated piping. The literaiure review on the angle of repose of various dry solids by Mrs. B. S. Neumann in J. J. Hermans' book on''Flow Properties of Dispersed Systems'' is summarized. Mrs. Neumann points out that both a dynamic and static angle of repose have been observed with the angles for dynamic systems being larger than for static systems. Results are reported for two different types of experiments with slurry discharged from run 200A-14 which gave static angles of repose of 45 to 50 deg and dynamic angles of 65 to 75 deg . (auth)
Date: February 14, 1958
Creator: Thomas, D. G.
Object Type: Report
System: The UNT Digital Library
COMPARATIVE BEHAVIOR OF A 1.8 ATOM % CHROMIUM-URANIUM ALLOY AND NORMAL URANIUM ON THERMAL CYCLING (open access)

COMPARATIVE BEHAVIOR OF A 1.8 ATOM % CHROMIUM-URANIUM ALLOY AND NORMAL URANIUM ON THERMAL CYCLING

None
Date: July 14, 1950
Creator: White, D.W.
Object Type: Report
System: The UNT Digital Library
The Compatibility of a Number of Metals and Alloys With Graphite (open access)

The Compatibility of a Number of Metals and Alloys With Graphite

The interaction between graphite and a number of metals and alloys was studied at 1850 deg F in 250-hr tests. Some materials were also tested at 1650 and 1850 deg F in 1000-hr tests. The graphite was heated in intimate contact with the test metal in welded metallic capsules. The exen of the reaction was judged on the basis of metallographic examinations and hardness traverses on cross sections of the reacted elements. Copper was the least reactive material tested in contact with graphite. Nickel was only slightly more reactive. Outside of a veny hard carbide band at the graphite-metal interface, no evidence of interaction of carbon with molybdenum was found. Inconel X was the most compatible alloy tested in contact with graphite, although some pickup was observed. Alnicro was the next best alloy. Nichrome V, Inconel, and Types 316 and 318 stainess steels were all much more reactive. Copper and chromium plating reduced the rate of diffusion of carbon into Type 316 stainless steel. Nickel plating was less effective for this purpose. (auth)
Date: April 14, 1958
Creator: Gerds, A.F. & Mallett, M.W.
Object Type: Report
System: The UNT Digital Library
A concrete shield-design (open access)

A concrete shield-design

It is shown that the use of Iron-Limonite shielding concrete and a steel frame structure can afford a saving of $1,351,000.00 when compared to 105 DR-H construction and material costs. C-431-B costs are not complete enough to use as basis except for the concrete materials. This study is based on actual records where possible and shows direct costs only. No allowances for transportation or tooling have been allowed in either case. An overall time saving on reactor shield construction of 30--60 days may be possible, but no significant change in the field erection time is anticipated.
Date: August 14, 1951
Creator: Jaske, R. T.
Object Type: Report
System: The UNT Digital Library
The continuous chlorination of plutonium dioxide (open access)

The continuous chlorination of plutonium dioxide

Previous reports on the chlorination of plutonium dioxide describe numerous small-scale experiments and a few fair-sized batch preparations. The chemistry of chlorination by numerous reagents is covered, but no process had received sufficient study for large-scale preparation of anhydrous plutonium trichloride. The literature search revealed no extensive studies on chlorination rates, exhaust gas filtering, atmospheric requirements, reactor materials, etc. A program was undertaken to select a chlorination process, to develop the necessary information for defining operating conditions and equipment specifications, and then to demonstrate the operation of the process.
Date: August 14, 1959
Creator: Rasmussen, M. J.
Object Type: Report
System: The UNT Digital Library
Correlation of cleanout and estimated product hold-up data - N-1 Nutsches (open access)

Correlation of cleanout and estimated product hold-up data - N-1 Nutsches

Data is presented from the separations technology division, May 14, 1951, to compare plutonium recovery from leaches of N-1 to corresponding hold-up data of plutonium.
Date: May 14, 1951
Creator: Healy, W.C.
Object Type: Report
System: The UNT Digital Library
Correlation of Polarographic Walf-Wave Potentials With Nuclear Magnetic Resonance "Chemical Shifts." Parallel Correlation With Chemical Reactivity Parameters. Report No. 35 (open access)

Correlation of Polarographic Walf-Wave Potentials With Nuclear Magnetic Resonance "Chemical Shifts." Parallel Correlation With Chemical Reactivity Parameters. Report No. 35

Since nuclear magnetic resonance ''chemical shifts'' are considered to be good measures of electron densities in molecules, the extent to which they can be correlated with the polarographic half-wave potentials of organic compounds has been surveyed. To extend the applicability and interpretation of the proposed correlation, parallel correlatioan of E, with Hammett's sigma and Taft's sigma parameters were made, since both of the latter are also regarded as indication of electronic distrinution at the reactive center. The data in general support the view that changes in half-wave potential with structure are due to both electronic and steric effects, as well as perhaps to adsorption phenomena. Significantly, NMR data obtained with one type of substituent could be correlated with E/sub 1/2 data for a similar type of substituent. New NMR data for aliphatic nitro and halogen compounds are reported. (auth)
Date: July 14, 1958
Creator: Bennett, C. E. & Elving, P. J.
Object Type: Report
System: The UNT Digital Library
Corrosion of Stainless Alloys in High-Temperature Nitrogenous Environments (open access)

Corrosion of Stainless Alloys in High-Temperature Nitrogenous Environments

On the basis of screening tests and favorable mechanical propenties, AISI Type 318 stainless steel was selected as a fuel-element cladding material to operate in c coolant comprised essentially of gaseous nitrogen modified by the addition of oxygen and water vapor. Tests at atmospheric pressure confirmed calculations which indicated that small additions of oxygen to nitrogen would inhibit nitriding by the process of preferential oxidation. The tests at atmospheric pressure determined that the rate of oxidation of Type 318 stainless was generally at a minimum when 0.5 volume per cent oxygen was added to the nitrogen gas. Oxidation of this steel was more severe when additions of 0.1 and 5.0 volume per cent oxygen were made to the nitrogen The rate of oxidation was primarily temperature dependent, but was also influenced by time. Oxidation during exposure periods of less than 1000 hr appeared to proceed at a parabolic rate. On longer exposures, however, there wcre indications of more rapid attack. A maximum depth of attack of 2.9 mils was observed on Type 318 stainless which had been exposed at 1650 F for 3658 hr. Stress-corrosion studies indicated that unstressed and stressed specimens were attacked at about the same rate. Stresses …
Date: July 14, 1959
Creator: Keller, D.L. ed.
Object Type: Report
System: The UNT Digital Library
COST COMPARISONS OF CAPITOL INVESTMENT IN VARIOUS NUCLEAR POWER PLANTS FOR CENTRAL STATION APPLICATION (open access)

COST COMPARISONS OF CAPITOL INVESTMENT IN VARIOUS NUCLEAR POWER PLANTS FOR CENTRAL STATION APPLICATION

The capital costs for a number of power reactors are compared after escalation to equivalent construction dates. It is shown that the most important factor affecting nuclear power plant capital costs is the net capacity of the plant. Steam conditions are shown to have a relatively minor effect on capital costs. (auth)
Date: October 14, 1958
Creator: Bender, M. & Stulting, R. D.
Object Type: Report
System: The UNT Digital Library
Cost of Blending Uranium of Two Different U$sup 235$ Isotopic Enrichments. Values of Uranium From The "USAEC Unclassified Pricing List" (open access)

Cost of Blending Uranium of Two Different U$sup 235$ Isotopic Enrichments. Values of Uranium From The "USAEC Unclassified Pricing List"

>Cost tables and instructions for calculating the cost of blending two different isotopic enrichments of U/sup 235/ to form an intermediate assay are presented. A sample calculation is included and information on reactor fuel cycles is given. (J. R. D.)
Date: October 14, 1958
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Creep Rupture in the Presence of a Fast Neutron Flux (open access)

Creep Rupture in the Presence of a Fast Neutron Flux

Possible mechanisms for creep rupture during irradiation are examined. Evidence that the rupture occurs by grain boundary sliding alone, or by vacancy condensation, is compared. It is observed that vacancy condensation is the more probable mechanism, and that this mechanism predicts a reduction in creep rupture life for metals exposed to a fast neutron flux (neglecting effects of radiation annealing). (T.F.H.)
Date: January 14, 1959
Creator: Gregory, D. P.
Object Type: Report
System: The UNT Digital Library
A critical mass study of Hood No. 5 and the filter boat cleaning and testing hood in the 234-5 Building (open access)

A critical mass study of Hood No. 5 and the filter boat cleaning and testing hood in the 234-5 Building

Calculations are presented for the estimated minimum critical mass of Pu that would be allowed in Hood No. 5 and the filter boat cleaning and testing hood of the Plutonium Finishing Plant. Hood No. 5 contains the overflow tank and two vacuum traps. Limits are given for several pile exposure rates. These limits do not allow the approach of personnel into Hood No. 5 when these vessels are full.
Date: July 14, 1955
Creator: Ketzlach, N.
Object Type: Report
System: The UNT Digital Library