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SM-1A PROJECT--TECHNICAL MANUAL: CHEMISTRY
A manual is given of the equipment and procedures used in the Army Reactor (SM-1A) to control the water purity and makeup. In addition to a description of the primary purification control system, a discussion is presented of the water chemistry control procedures for the auxiliary systems (e.g., the spent-fuel pit, the shield tank, and the waste disposal system). (T.F.H.)
Date:
September 29, 1960
Creator:
Chupak, J.
Object Type:
Report
System:
The UNT Digital Library
Loading, Shipping and Testing Procedures for Task 2 Isotopic Powered Thermoelectric Generator. Preliminary Technical Manual
A preliminary report on the operations and procedures for handling a 125- w thermoelectric generator and its isotopic heat source is presented. Full-scale mock-ups were used to develop the procedures. A cylindrical metal block of Inconel X will be remotely loaded with an isotope at ORNL. The block will then be sealed snd loaded into a specially designed cask and shipped by rail to the Martin nuclear hot cell facility, where the second phase of the operation will be conducted. (W.D.M.)
Date:
March 24, 1960
Creator:
Reilly, M. J.
Object Type:
Report
System:
The UNT Digital Library
Instruction Manual, Mercury Relay Pulse Generator Model 1-1212C
The Model Q-1212C Pulser is a single frequency (60 pps) generator whose output waveform is characterized by a rise-time of less than 4 mµsec and, depending upon the method of termination, an exponential decay having a time constant of 300 or 600µsec. The waveform approximates that produced by a radiation detector. The waveform approximates that produced by a radiation detector. The maximum available output from the instrument is 10 volts, positive or negative polarity, and is continuously adjustable by means of step switches and a 10-turn potentiometer. The potentiometer has a linearity of 0.1%.
Date:
September 20, 1960
Creator:
Fairstein, E.
Object Type:
Report
System:
The UNT Digital Library
OPERATING MANUAL FOR THE AE-6 REACTOR
An attempt is made to provide a single reference source for material pertinent to the maintenance and operation of the AE-6 Reactor. Descriptions of various components are included, as well as the common operational and maintenance procedures and check lists. Information is given on the subcritical assemblies that may be studied. (W.D.M.)
Date:
June 23, 1960
Creator:
Moore, E.A. Jr.
Object Type:
Report
System:
The UNT Digital Library
CEND CRITICAL FACILITIES OPERATIONS MANUAL. BONUS CRITICAL EXPERIMENT.
None
Date:
January 1, 1960
Creator:
Knapp, R W
Object Type:
Report
System:
The UNT Digital Library
Multi-Purpose Dissolver Information Manual
The multi-purpose dissolver was designed to provide: 1. A critically safe vessel for dissolving uranium metal of enrichments up to one percent U-235. 2. A vessel which can be charged with fuel elements up to 10 feet long. 3. An off-gas arrangement which will eliminate return of ammonia to the dissolver during the Zirflex decladding process. 4. A vessel in which small charges can be dissolved without using extra chemicals. 5. A by-pass routing around the silver reactor during cladding removal.
Date:
March 4, 1960
Creator:
Simonds, H. P.
Object Type:
Report
System:
The UNT Digital Library
Technical description of the new SS accountability program on the IBM-709
The SSA 100 program will compute the buildup and decay of SS materials, (gms Pu, U-235 burnout and uranium burnout) in fuel that has been irradiated in any of the Hanford reactors. The routine input data for the program are the IBM production records supplied by the Production Forecasting and Scheduling Operation. The purpose of this program is to compute and prepare an accurate accountabilty report with a minimum of manual effort. This can either be a report for fuel discharges from the reactors or a report of the entire month end reactor inventory. It is not the purpose of this report to describe in detail the data processing techniques used to provide the accountability reports, this will be left to the discretion of the SS Accountability Operation and the programer. The purpose of this report is to present (1) the technical methods that are fundamental to the program, (2) the necessary instructions that are necessary to make changes or include additional fuel data on the data tape and (3) the necessary instructions such that buildup and decay data can be obtained for fuel elements on a non-routine basis.
Date:
January 7, 1960
Creator:
Richey, C. R.
Object Type:
Report
System:
The UNT Digital Library
Electrical Design Standards and Graphical Symbols
This manual represents the recommendations of the Instrumentation and Controls Division committee on Electrical and Electronic Symbols and Drawing that have been issued to date, and supersedes the previously issued ORNL Electrical Symbols List and CF-58-12-141, Electrical and Electronic Drawing Standards for Wiring and Device Coding and Applications.
Date:
October 1960
Creator:
Bates, A.E.G; Bowelle, M.M.; Horton, J. L.; Moore, R. L.; Hyland, R. F. & Brashear, C.
Object Type:
Report
System:
The UNT Digital Library
BETTIS TECHNICAL REVIEW. REACTOR TECHNOLOGY
This review covers research on irradiation effects, sintering of oxides, mechanical and physical properties of materials, film gages, hydrodynamics, and fuel elements. Separate abstracts have been prepared for the 10 papers. (W.L.H.)
Date:
September 1, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Manual of Radiation Protection Standards
"The following is an alphabetical listing of terms and units in common usage at Hanford Atomic Products Operation. Other terms and definitions may be added as the need becomes apparent or as revisions or additional terms are issued by the NCRP and ICRP."
Date:
March 1, 1960
Creator:
General Electric Company
Object Type:
Report
System:
The UNT Digital Library
Technical bases for C-pile overbore test
The production gains and economic evaluation of overboring has been extensively treated. In this document, the justification for a trial attempt at overboring C-Reactor was given. The overboring test, covered by two production tests (one or overboring and one for fuel irradiation), requires the integration of efforts of Equipment Development, Process and Reactor Development, Process Technology, Manufacturing, and the Fuels Preparation Department. In view of this, it appears prudent to collect in one place the current design numbers with a word of explanation regarding their derivation. To this end, this document is dedicated.
Date:
November 3, 1960
Creator:
Curtiss, D. H.; Clinton, M. A. & Nechodom, W. S.
Object Type:
Report
System:
The UNT Digital Library
A Transistorized Reactivity Measurement System
An all-transistor system has been developed to be used in measuring the reactivity of the reactor in the Sandia Engineering Reactor Facility. In operation, the system triggers a pulsed neutron source (PNS) in the reactor and counts the resulting neutron flux, thus giving a measure of the time constant of the reactor. The counting is done in eleven time-sequenced counting channels. The reactor time constant is a measure of the reactor reactivity.
Date:
July 6, 1960
Creator:
Ehrman, Leonard
Object Type:
Report
System:
The UNT Digital Library
High Velocity Shock Testing, Equipment and Methods
The need for special high velocity shock testing is pointed out and equipment that has been developed to meet these needs is discussed. The concept of velocity-change and its importance in shock-testing technology is brought out. The three types of equipment discussed are: accelerated drop testers, pneumatic actuators, and air guns. Examples of each type and their capabilities and limitations are presented.
Date:
July 11, 1960
Creator:
Walker, Walter W.
Object Type:
Report
System:
The UNT Digital Library
Idaho Chemical Processing Plant Technical Progress Report for January- March 1960
9 > ? ( ing schedule included MTR, ETR, and other aluminum-type fuels that were processed through the TBP headend at 75 to 100% of flowsheet rates and through the Hexone second and third cycle extraction system at up to l5O% of flowsheet values, achieving an over-all recovery of 99.60%. In carrying out basic studies on aqueous zirconium processing, results obtained during the potentiometric titration of zirconium-fluoride-nitric acid solutions with sodium hydroxide were explained by a mechanism in which the untitrated zirconium fluoride species is converted to a fluozirconate and further hydrolysis proceeds via a fluozirconate route. A modified Zirflex flowsheet for processing 2.5% U-Zr alloy fuels is proposed as a result of bench scale dissolution studies on unirradiated PWR plates that showed that dissolver solutions could be stabilized by adding aluminum nitrate and nitric acid. that higher ammonium fluoride concentrations increased the dissolution rate, that higher hydrogen peroxide concentrations lowered the dissolution rate and decreased solution stability, and that ammonia removal by boiling with or without air sparging had little effect on the reaction. Density curves for Zirflex solutions are reported. First tests of the pilot plant for continuous dissolution of zirconium-type elements have indicated that the dissolution rate …
Date:
July 13, 1960
Creator:
Slansky, C.M.; Warzel, F.M. & Bower, J.R. Jr. ed.
Object Type:
Report
System:
The UNT Digital Library
IDAHO CHEMICAL PROCESSING PLANT TECHNICAL PROGRESS REPORT, OCTOBER-DECEMBER 1959
None
Date:
May 26, 1960
Creator:
Bower, J.R. Jr. ed.
Object Type:
Report
System:
The UNT Digital Library
PATHFINDER ATOMIC POWER PLANT TECHNICAL PROGRESS REPORT, APRIL 1960-JUNE 1960
None
Date:
October 15, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Civilian Power Reactor Program. Part 1. Summary of Technical and Economic Status as of 1959
The current technical and economic status for each reactor concept in the Civilian Power Reactor Program is summarized. The individual techical status reports which present detailed information will be published by AEC as TID-8518. Included in this summary are: power costs for various reactor types versus coal- fired plants; construction schedule for heavy-water natural-U reactors; and annual program costs. (T.R.H.)
Date:
January 1, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
IDAHO CHEMICAL PROCESSING PLANT TECHNICAL PROGRESS REPORT FOR JULY THROUGH SEPTEMBER 1959
None
Date:
June 12, 1960
Creator:
Stevenson, C.E.
Object Type:
Report
System:
The UNT Digital Library
PATHFINDER ATOMIC POWER PLANT TECHNICAL PROGRESS REPORT, JANUARY 1960-MARCH 1960
None
Date:
June 15, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
PATHFINDER ATOMIC POWER PLANT TECHNICAL PROGRESS REPORT FOR OCTOBER 1959- DECEMBER 1959
>Technical progress on the research and development program being performed in connection with the design of the Sioux Falls Power Reactor is reported. Areas covered in detail include fuel element research and development, reactor mechanical studies, nuclear analysis, chemistry, instrumentation and control, plant safety analysis, feasibility studies, and steam plant and reactor auxiliary systems design. (For preceding period see ACNP-5924.) (W.D.M.)
Date:
March 15, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Analysis of Uranium Fuel-Element Wafers from Atomics International for Uranium, Plutonium and Samarium
Five irradiated and five unirradiated wafers were analyzed. Each wafer was analyzed for samarium by emission spectrography. The unirradiated wafers were analyzed for uranium by coulometric and potentiometric methods and for uranium isotopes by mass spectrometry. The irradiated wafers were analyzed for uranium and plutonium by coulometric methods, for plutonium isotopes by the 256-channel alpha pulse analyzer, and for the isotopes of uranium and of plutonium by mass spectrometry. The methods of preparing wafers for analysis are discussed; the data are tabulated.
Date:
December 27, 1960
Creator:
Gaitanis, M. J.
Object Type:
Report
System:
The UNT Digital Library
Equipoise-2: A Two-Dimensional, Two-Group, Neutron-Diffusion Code for the IBM-7090 Computer
Equipoise-2, a two-dimensional, two-group neutron-diffusion code in R-Z geometry, has been programmed for the IBM-7090 computer. This code was designed to permit the running of large numbers of cases without requiring excessive machine time. Typical running times are of the order of one to three minutes per case for a 1000-point problems. The maximum number of mesh points that can be used is 1444.
Date:
November 21, 1960
Creator:
Fowler, T. B. & Tobias, Melvin
Object Type:
Report
System:
The UNT Digital Library
A Transport Calculation of the HFIR Beam Hole Currents
An estimate was made of the beam hole currents to be expected from both the radial and tangential beam holes in the present HFIR design. The angular fluxes required for these calculation were determined by an 18-group, S8 transport calculation (SNG reactor code). Both type beam holes produced thermal neutron currents of 7.5 x 10^10 neutrons/cm^2 sec. at a power level of 100 Mw. The nonthermal component of the beam current was 7.0 x 10^10 and 4.5 x 10^10 neutrons/cm^2 -sec for the radial and tangential holes, respectively.
Date:
December 5, 1960
Creator:
Claiborne, H. C. & Rakavy, G.
Object Type:
Report
System:
The UNT Digital Library
Specifications for Fuel Assemblies for Core I of the Experimental Gas-Cooled Reactor
These specifications for the fuel assemblies for Core I of the Experimental Gas-Cooled Reactor (EGCR) have been developed for use in procuring the first core loading. A fuel assembly for EGCR consists of a cluster of seven cylindrical fuel elements spaced and supported within a graphite sleeve. Each fuel element consists of a stainless steel tube containing a column of hollow UO2 pellets and having a spacer brazed at the midsection to control the spacing between fuel elements in a cluster. A master specification for the fuel assembly, a supplementary specification for each of the components, and a specification on record keeping during manufacture are included.
Date:
December 9, 1960
Creator:
Coobs, J. H.; Wick, E. A. & Evans, R. M.
Object Type:
Report
System:
The UNT Digital Library