UNT Libraries Government Documents Department - 201 Matching Results

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Activity Build-Up Control by High pH Coolant. A Literature Survey

Description: A survey was made of unclassified literature dealing with the control of activity build-up in pressurized water reactors by high-pH coolants. Survey results indicate that a high-pH coolant is desirable for control of induced radioactivity build-up in pressurized water reactors containing significant amounts of stainless steel and that no significant hazards are introduced by adoption of a high-pH coolant. Lithium hydroxide was found to be the most acceptable agent for coolant pH control. Strong… more
Date: January 23, 1961
Creator: Bergen, C. R.
Item Type: Refine your search to only Report
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Amine Extraction of Plutonium From Nitric Acid Solutions Loading and Stripping Experiments

Description: Information is presented on a suitable amine processing system for plutonium nitrate. Experiments with concentrated plutonium nitrate solutions show that trilaurylamine (TLA) - xylene solvent systems did not form a second organic phase. Experiments are also reported with tri-noctylamine (TnOA)-xylene and TLA-Amsco - octyl alcohol. Two organic phases appear in both these systems at high plutonium nitrate concentrations. Data are tabulated from loading and stripping experiments. (J.R.D.)
Date: January 19, 1961
Creator: Wilson, A. S.
Item Type: Refine your search to only Report
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An Analogue Solution of a Reactor Perturbation Initiated by a Metallurgical Phase Transformation of the Fuel

Description: The analysis of a reactor model that is thermally nonlinear is presented. The significant sources of feadback in the closed-loop model ane dilatational changes of the fuel due to axial expansion caused by temperature and metallurgical phase changes. Ths dynamics of this phenomenon has been represented on the Pace electronic analog com puter. The model was subjected to unusually large inputs of sinusoidal power and did not show any drastic tendencies toward being unstable. (auth)
Date: January 1, 1961
Creator: Bryant, L. T.; Carter, J. C. & Janicke, M. J.
Item Type: Refine your search to only Report
open access

An Analysis of Inconsistencies in Removal Cross Sections of Carbon and Oxygen

Description: Abstract. Some recent analysis of certain Lid Tank fast neutron dose rates measured in oil and water indicates that there are some basic inconsistencies with reported oxygen and carbon removal cross sections and the reported data. These inconsistencies may be explained in several ways: (1) The reported carbon removal cross section is wrong. (2) The reported oil composition is wrong. (3) The reported oxygen removal cross section is wrong since it is based on an assumed rather than a measured o… more
Date: January 20, 1961
Creator: {{{name}}}
Item Type: Refine your search to only Report
open access

Analysis of P&W NJ-18A Power Plant Pressure Drop Between Compressor Discharge and Turbine Inlet

Description: This study is part of an evaluation of the P&W NJ- 18A powerplant. The work presented here specifically estimates the pressure drop between the compressor discharge and the turbine inlet. Analysis was asked for two operating conditions. One was for sea level sprint at a Mach no. of 0.9, while the other was for a Mach no. of 0.9 at 35000 ft.
Date: January 3, 1961
Creator: Casagrande, R. D.
Item Type: Refine your search to only Report
open access

Analysis of the Initial Nuclear Superheat Critical Experiments. Supplementary Study Related to Bonus and Nuclear Superheat Programs

Description: A critical experiment program is carried out in a configuration similar to the BONUS reactor. The results give information concerning: the effects of different boilersuperheater geometries; the reactivity changes associated with superheater voiding or flooding; power regulation between the boiler and superheater regions; epithermal transmission probabilities for B-stainless steel and Cd control rods; the power flattening characteristics; and void simulation properties. The calculational methods… more
Date: January 30, 1961
Item Type: Refine your search to only Report
open access

Application of Amides as Extractants

Description: Technical report. From Abstract : "Laboratory data are given and discussed that outline the potential application of N, N-distributed amides to the separation of uranium, neptunium, and plutonium from fission products."
Date: January 1961
Creator: Siddall, Thomas H., III
Item Type: Refine your search to only Report
open access

ARGONAUT REACTOR DATA-BOOK. A compilation of experimental and theoretical results of work done with, or related to, the Argonaut Reactor to July 1960

Description: This compilation was prepared to provide a comprehensive unified summary of the principal elements of the design, operation and nuclear characteristics of the Argonaut Reactor. Its primary content is made up of the theoretical and experimental evaluations of basic reactor parameters, both static and kinetic, which have been made to this date. The Databook includes also some practical information on the reaativity worths of fuel, moderator, and absorbers, as well as some data on radiation in the… more
Date: January 1, 1961
Creator: Sturm, W.J. & Daavettila, D.A.
Item Type: Refine your search to only Report
open access

B-Plant fission product flowsheets. Part 1

Description: B-Plant is currently being evaluated for use as an integrated fission product plant operating in conjunction with the Purex Plant and a waste calcination system. If the forecasted demands for fission products should increase to rates exceeding present capabilities and if private enterprise continues to remain outside the recovery field, present budget plans are to develop the use of B-Plant in three phases. In Phase 1, the B-Plant canyon would be activated and provisions made for preparing and … more
Date: January 12, 1961
Creator: Beard, S. J. & Judson, B. F.
Item Type: Refine your search to only Report
open access

Birch Plant Improvement Program

Description: The Birch Plant Improvement Program is described in this document. This program was instituted to fully support the AEC program for maximum recovery of neptunium from current separations feed material and other sources as the AEC may consider appropriate to their needs for increasing the availability of neptunium.
Date: January 20, 1961
Creator: Fecht, J. B.
Item Type: Refine your search to only Report
open access

BRIC-AN IBM-704 TWO-DIMENSIONAL NUCLEAR-THERMAL DEPLETION PROGRAM WITH DISTRIBUTED VOID EFFECTS

Description: BRIC is a two-dimensional nuclear-thermal depletion program to study the effects of moderator boiling on the neutron flux distribution and the depletion of the timedependent isotopes. The program requires an IBM-704 with a memory of 32,768 words and ten tape units. (auth)
Date: January 1, 1961
Creator: Jacobi, W. M.; Lawton, T. J.; Meanor, S. H. & Parrette, J. R.
Item Type: Refine your search to only Report
open access

The Calculation of Nonlinear Radiation Transport by a Monte Carlo Method

Description: A monte Carlo method of solving the one-dimensional equations of nonlinear radiation transport is compared with the Sn "characteristics" method of solution. It is concluded that the Monte Carlo method is accurate and stable and furthermore for a given time-cycle length and space-zone size the Monte Carlo method is more accurate than the Sn method.
Date: January 1, 1961
Creator: Fleck, J. A., Jr.
Item Type: Refine your search to only Report
open access

CHARACTERISTICS OF RADIOACTIVITY PRODUCED BY NUCLEAR EXPLOSIVES

Description: The amounts and kinds of radioactivities produced by detonation of a nuclear explosive are dependent upon the specific design of the explosive. The two design extremes are a pure fission device, which will produce about 1.4 x 10/ sup 23/ fissions, and therefore about 2.8 x 10/sup 23/ fission products, per kiloton of energy released, and a pure thermonuclear device which would produce no fission products, but would produce approximately 10/sup 23/ atoms of tritium per kiloton. In both cases, int… more
Date: January 1, 1961
Creator: Miskel, J A
Item Type: Refine your search to only Report
open access

CHARGING AND DISCHARGING OF DEMINERALIZER RESINS. CORE I, SEED 2. Test Results (T-612085). Section 1

Description: An investigation was conducted to flush the 1BD coolant purification system demineralizer of resin and to measurc the radiation level at pornts on the resin discharge line. It was found that the system demineralizer was satisfactorily flushed of resin. It was also found that the amount removed is measured by the amount required to recharge the demineralizer. (J.R.D.)
Date: January 10, 1961
Item Type: Refine your search to only Report
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