External-Fuel Thermionic Reactors (open access)

External-Fuel Thermionic Reactors

The concept of the external-fuel thermionic converter, in which the fuel surrounds an inner emitter annulus, is introduced and the major advantages of its use in a thermionic reactor are discussed. In-core reactors, ranging from 15-ekW to megawatts, can be designed based on external-fuel converter modules of fixed emitter and collector dimensions. Sizes and weights of typical reactors in this power range are shown.
Date: May 1, 1968
Creator: Abbate, M. J.; Eisen, C. L.; Raab, B. & Schock, Alfred
Object Type: Report
System: The UNT Digital Library
Reactor Development Program Progress Report: April 1963 (open access)

Reactor Development Program Progress Report: April 1963

Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during April 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: May 15, 1963
Creator: Adams, R. M. & Glassner, A.
Object Type: Report
System: The UNT Digital Library
The Role of Oxygen in Solid State Polymerization. [Part] 1. Acrylamide and Its Solid Solutions (open access)

The Role of Oxygen in Solid State Polymerization. [Part] 1. Acrylamide and Its Solid Solutions

None
Date: May 18, 1965
Creator: Adler, G.
Object Type: Report
System: The UNT Digital Library
High Dilution On-Stream Isotopic Tracers Annual Report: 1961 (open access)

High Dilution On-Stream Isotopic Tracers Annual Report: 1961

Introduction: The primary objective of the work of this report was research and development leading to large-scale applications of low level isotope tracer technology.
Date: May 1961
Creator: Aebersold, Paul C. & Bizzell, Oscar M.
Object Type: Report
System: The UNT Digital Library
Economic and Demographic Characteristics of the Alamo Area Council of Governments Area: An Overview (open access)

Economic and Demographic Characteristics of the Alamo Area Council of Governments Area: An Overview

This report is designed to provide basic information about an initial analysis of the major economic and demographic characteristics of the eight counties included within the Alamo Area Council of Governments. The uses of this information include primarily the development of a comprehensive Social Planning Program for the area designed to meet the social service needs of the entire metropolitan area.
Date: May 1969
Creator: Alamo Area Council of Governments
Object Type: Text
System: The Portal to Texas History
Letter to Mr. Frank Rom, National Aeronautics and Space Administration, Lewis Research Center, Cleveland, Ohio (open access)

Letter to Mr. Frank Rom, National Aeronautics and Space Administration, Lewis Research Center, Cleveland, Ohio

None
Date: May 20, 1965
Creator: Albaugh, F. W.
Object Type: Report
System: The UNT Digital Library
Pacific Northwest Laboratory Monthly Activities Report, Division of Biology and Medicine Programs: April 1969 (open access)

Pacific Northwest Laboratory Monthly Activities Report, Division of Biology and Medicine Programs: April 1969

Progress is updated for projects related mostly to biological and ecological radiation effects.
Date: May 1, 1969
Creator: Albaugh, F. W.
Object Type: Report
System: The UNT Digital Library
Reactor and Materials Technology monthly report, April 1965 (open access)

Reactor and Materials Technology monthly report, April 1965

This report details activities of the Reactor and Materials Technology Department during the month of April 1965.
Date: May 14, 1965
Creator: Albaugh, F. W.
Object Type: Report
System: The UNT Digital Library
Final report: PITA-18 use of nonpoisonous splines for longitudinal flux traversing (open access)

Final report: PITA-18 use of nonpoisonous splines for longitudinal flux traversing

Optimization of the reactor process involves the knowledge of the longitudinal flux distribution on a semicontinuous, routine basis. The nonpoisonous spline was proposed as a way for obtaining flux traverses at any time during reactor operation, in virtually any location in the core. This report summarizes the findings of a feasibility study conducted in conjunction with PITA-18 and thus serves as a termination of the test phase of spline traversing.
Date: May 1, 1963
Creator: Albertson, D. G. & Bowers, C. E.
Object Type: Report
System: The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures (open access)

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures

Operation and maintenance procedures for 30 megawatt heat exchanger and steam generator for sodium cooled reactor system.
Date: May 15, 1962
Creator: Alco Products (Firm)
Object Type: Report
System: The UNT Digital Library
Scale "Up or Down" Analysis for Prototype Test (open access)

Scale "Up or Down" Analysis for Prototype Test

Introduction: In conjunction with the final design and development of a 70 MW sodium intermediate heat exchanger and a sodium steam generator, an analysis is required which can be used as a basis for a determination to scale up or scale down the designs. Included in this analysis are those considerations leading to the recommendation of the best prototype test unit and to some of the limits imposed on scaling up or down when considering future applications of designs other than those actually tested. In addition, these considerations include aspects required to accurately predict the performance, operation, mechanical reliability, and feasibility of fabrication of the 70 MW design.
Date: May 1, 1960
Creator: Alco Products (Firm).
Object Type: Report
System: The UNT Digital Library
THORIUM BREEDER REACTOR EVALUATION. PART 1. FUEL YIELD AND FUEL CYCLE COSTS IN FIVE THERMAL BREEDERS (open access)

THORIUM BREEDER REACTOR EVALUATION. PART 1. FUEL YIELD AND FUEL CYCLE COSTS IN FIVE THERMAL BREEDERS

The performances of aqueous-homogeneous (AHBR), molten-salt (MSBR), liquid-bismuth (LBBR), gas-cooled graphite-moderated (GGBR), and deuterium- moderated gas-cooled (DGBR) breeder reactors were evaluated in respect to fuel yield, fuel cycle costs, and development status. A net electrical plant capability of 1000 Mwe was selected, and the fuel and fertile streams were processed continuously on-site. The maximum annual fuel yields were 1.5 mills/ kwhr. The minimum estimated fuel cycle costs were 0.9, 0.6, 1.0, 1.2, and 1.3 mills/kwhr at fuel yields of were 0.9, 0.9, 1.5, 1.5, and 1.3 mills/kwhr. Only the AHBR and the MSBR are capable of achieving fuel yields substantially in excess of 4%/yr, and therefore, in view of the uncertainties in nuclear data and efficiencies of processing methods, only these two can be listed with confidence as being able to satisfy the main criterion of the AEC longrange thorium breeder program, viz. a doubling time of 25 years or less. The development effort required to bring the various concepts to the stage where a prototype station could be designed was estimated to be least for the AHBR, somewhat more for the MSBR, and several times as much for the other systems. The AHBR was judged to rank first in …
Date: May 24, 1961
Creator: Alexander, L. G.; Carter, W. L.; Chapman, R. H.; Kinyon, B. W.; Miller, J. W. & Van Winkle, R.
Object Type: Report
System: The UNT Digital Library
Thorium Breeder Reactor Evaluation. Part I. Fuel Yield and Fuel Cycle Costs in Five Thermal Breeders (open access)

Thorium Breeder Reactor Evaluation. Part I. Fuel Yield and Fuel Cycle Costs in Five Thermal Breeders

The performances of aqueous-homogeneous (AHBR), molten-salt (MSBR), liquid-bismuth (LBBR), gas cooled graphite-moderated (GGBR), and deuterium-moderated gas-cooled (DGBR) breeder reactors were evaluated in respect to fuel yield, fuel cycle costs, and development status. A net electrical plant capability of 1000 Mwe was selected, and the fuel and fertile streams were processed continuously on-site.
Date: May 24, 1961
Creator: Alexander, L. G.; Carter, W. L.; Chapman, R. H.; Kinyon, B. W.; Miller, J. W. & Van Winkle, R.
Object Type: Report
System: The UNT Digital Library
THORIUM BREEDER REACTOR EVALUATION. PART I. FUEL YIELD AND FUEL CYCLE COSTS IN FIVE THERMAL BREEDERS. APPENDICES (open access)

THORIUM BREEDER REACTOR EVALUATION. PART I. FUEL YIELD AND FUEL CYCLE COSTS IN FIVE THERMAL BREEDERS. APPENDICES

The performances of aqueous-homogeneous (AHBR), molten-salt (MSBR), liquid-bismuth (LBBR), gas-cooled graphite-moderated (GCBR), and deuterium- moderated gascooled (DGBR) breeder reactors were evaluated in respect to fuel yield, fuel cycle costs, and development status. A net electrical plant capability of 1000 Mwe was selected with continuous processing of fuel and fertile streams. The maximum annual fuel yields were 16, 7, 4, 4, and 4.5%/yr, respectively at a fuel cycle cost of 1.5 mills/kwhr. The minimum estimated fuel cycle costs were 0.9, 0.6, 1.0, 1.2, and 1.3 mills/kwhr at fuel yields of 7, 1, 1, 2, and 3%/yr. At a fuel yield of 4%/yr, the costs were 0.9, 0.9, 1.5, 1.5, and 1.3 mills/kwhr. Only the AHBR and the MSBR are capable of achieving fuel yields substantially in excess of 4%/yr, and therefore only these two can be listed with confidence as being able to satisfy the mdin criterion of the AEC long-range thorium breeder program i.e., a doubling time of 25 years or less. The development effort required to bring the various concepts to the stage where a prototype station could be designed was estimated to be least for the AHBR, somewhat more for the MSBR, and several times as much for …
Date: May 24, 1961
Creator: Alexander, L. G.; Carter, W. L.; Chapman, R. H.; Kinyon, B. W.; Miller, J. W. & Van Winkle, R.
Object Type: Report
System: The UNT Digital Library
Thorium Breeder Reactor Evaluation. Part I. Fuel Yield and Fuel Cycle Costs in Five Thermal Breeders. Appendices (open access)

Thorium Breeder Reactor Evaluation. Part I. Fuel Yield and Fuel Cycle Costs in Five Thermal Breeders. Appendices

The performances of aqueous-homogeneous (AHBR), molten-salt (MSBR), liquid-bismuth (LBBR), gas-cooled graphite-moderated (GCBR), and deuterium-moderated gas-cooled (DGBR) breeder reactors were evaluated in respect to fuel yield, fuel cycle costs, and development status. A net electrical plant capability of 1000 Mwe was selected, and the fuel and fertile streams were processed continuously on-site.
Date: May 24, 1961
Creator: Alexander, L. G.; Carter, W. L.; Chapman, R. H.; Kinyon, B. W.; Miller, J. W. & Van Winkle, R.
Object Type: Report
System: The UNT Digital Library
NPR delayed neutron fractions and decay constants (open access)

NPR delayed neutron fractions and decay constants

This report discusses the delayed neutron characteristics of a reactor which are a function of the distribution of fissions in the various fissionable isotopes. The delayed neutron characteristics of the NPRL delayed fraction and decay constants, are presented as functions of exposure to 2000 MWD/T for both room temperature and operating temperature. It is of importance to note that the delayed neutron fraction decreases from 0.693% to 0.539% with increased exposure. Thus 22% less reactivity change represents a prompt critical condition at 2000 MWD/T, compared to the zero exposure condition.
Date: May 26, 1961
Creator: Allen, C. W.
Object Type: Report
System: The UNT Digital Library
A STUDY OF RESONANCES OF THE Z-7r SYSTEM (open access)

A STUDY OF RESONANCES OF THE Z-7r SYSTEM

Recently a T = 1 resonance in the {Lambda}-{pi} system called Y{sub 1} has been observed with a mass of 1385 MeV. Two types of resonances have been predicted that might relate this observation to other elementary-particle interactions: (1) P 3/2 resonances in the {Lambda}-{pi} and {Sigma}-{pi} systems predicted by global symmetry, corresponding to the (3,2/ 3/2) resonance of the {pi}-N system, (2) a spin-1/2 Y-{pi} resonance resulting from a bound state in the {bar K}-N system. The position and the width of the observed Y{sub 1} resonance agree with both theories, but since the spin and parity have not yet been determined, they cannot distinguish between the two theoretical interpretations.
Date: May 23, 1961
Creator: Alston, M.H.; Alvarez, L.W.; Eberhard, P.; Good, M.L.; Graziano,W.; Ticho, H.K. et al.
Object Type: Report
System: The UNT Digital Library
Critical Studies of a Dilute Oxide Fast Reactor Core (ZPR-III Assembly 30) (open access)

Critical Studies of a Dilute Oxide Fast Reactor Core (ZPR-III Assembly 30)

BS>Critical studies of a fast reactor core containing a simulated oxide fuel having an oxygen-uranium atomic ratio of 1: 1 are described. Calculated and experimental critical masses are compared. Experimental results are given for fission ratio, central reactivity coefficient, fuel bunching, and distributed worth measurements. (auth)
Date: May 1961
Creator: Amundson, P. I.; Hess, A. L.; Keeney, W. P.; Long, J. K. & McVean, R. L.
Object Type: Report
System: The UNT Digital Library
CLIP 1--AN IBM-704 PROGRAM TO SOLVE THE P-3 EQUATIONS IN CYLINDRICAL GEOMETRY (open access)

CLIP 1--AN IBM-704 PROGRAM TO SOLVE THE P-3 EQUATIONS IN CYLINDRICAL GEOMETRY

A second order form of the cylindrical P-3 equations is obtained for the case of an isotropic source. The boundary conditions and numerical method are discussed. Input preparation and operating instructions are included. (auth)
Date: May 1, 1962
Creator: Anderson, B.; Davis, J.; Gelbard, E.; Jarvis, P. & Pearson, J.
Object Type: Report
System: The UNT Digital Library
BAND-1--A DATA REDUCTION PROGRAM FOR THE IBM-704 (open access)

BAND-1--A DATA REDUCTION PROGRAM FOR THE IBM-704

BAND-1 is an IBM-704 program to reduce the experimental data obtained from measurements of the neutron activation distribution within a critical facility. The data reduction consists of correcting the measured data, sorting and ordering it, and calculating the critical buckling parameters by means of a least squares analysis. (auth)
Date: May 1, 1961
Creator: Anderson, B.L.; Hemphill, A.P.; Jarvis, P.H. & Kettler, R.E.
Object Type: Report
System: The UNT Digital Library
Preliminary petrographic study of rock from Nevada Test Site - Basalt Mesa (open access)

Preliminary petrographic study of rock from Nevada Test Site - Basalt Mesa

Discussing photographs of rocks from Basalt Mesa
Date: May 6, 1960
Creator: Anderson, E. E.
Object Type: Report
System: The UNT Digital Library
Strange-Particle Production by 1170-MeV/c pi- Mesons (open access)

Strange-Particle Production by 1170-MeV/c pi- Mesons

Production of {Lambda} + K{sup 0}, {Sigma}{sup 0} + K{sup 0}, and {Sigma}{sup -} + K{sup +} by 1170-MeV/c {pi}{sup -} mesons has been studied in the Lawrence Radiation Laboratory 72-inch hydrogen bubble chamber, Cross sections, angular distributions, and polarizations are presented. The polarization of the {Sigma}{sup 0} is determined at four center-of-mass angles and found to be small everywhere. Based on published results for the reaction {pi}{sup +} + p {yields} {Sigma}{sup +}, K{sup +}, a comparison of the polarizations of {Sigma}{sup +}, {Sigma}{sup -}, and {Sigma}{sup 0} is made from the charge-independence triangle. A conclusion is reached that the {Sigma}{sup -} polarization should be large, and that the {Sigma}{sup -} and {Sigma}{sup +} polarizations should be opposite in sign.
Date: May 27, 1963
Creator: Anderson, Jared Arnold
Object Type: Thesis or Dissertation
System: The UNT Digital Library
METALLOGRAPHY OF URANIUM CONTAINING SMALL ADDITIONS OF IRON, SILICON, OR ALUMINUM (open access)

METALLOGRAPHY OF URANIUM CONTAINING SMALL ADDITIONS OF IRON, SILICON, OR ALUMINUM

In uranium with alloying additions of up to 400 ppm Fe and up to 800 ppm of either Si or Al, the various U-containing phases were examined with the electron microscope. These phases were also extracted chemically and identified by electron diffraction. During gamma -phase heat treatments, the alloying additions, as well as impurity atoms, segregate into networks of incipient'' precipitates that can be seen only afier certain etching treatments. (auth)
Date: May 1, 1963
Creator: Angerman, C. L. & Louthan, M. R. Jr.
Object Type: Report
System: The UNT Digital Library
The Influence of Isotopic Composition on the Maximum in the Cosmic Ray Energy Spectra (open access)

The Influence of Isotopic Composition on the Maximum in the Cosmic Ray Energy Spectra

"The previously found maximum in the cosmic radiation energy spectrum is discussed, and the possibility that it arises in part from a misinterpretation of the data due to oversimplifying assumptions about the composition of the beam is examined. The importance that lack of recognition of isotopic composition may have is pointed out, and it is clear that this importance is strongly dependent on the measurements made and on the cut-off rigidity."
Date: May 8, 1961
Creator: Appa Rao, M.V.K. &
Object Type: Report
System: The UNT Digital Library