A 200-Watt Conduction-Cooled Reactor Power Supply for Space Application (open access)

A 200-Watt Conduction-Cooled Reactor Power Supply for Space Application

The limited supply of relatively long-half-life isotopes having a reasonably high power density and the low conversion efficiencies obtainable with thermoelectric devices have so far limited the power output of isotope-fueled sources of electric power to several tens of watts. In addition, the high cost of the available isotopes results in a very large expense for isotope-fueled generators producing several hundred watts. It appears that a small, minimumweight, conduction-cooled reactor is an attractive alternate to the isotope-fueled power supplies in the 200-w size range. The proposed reactor is a small, high-density fast core of U/sup 233/ surrounded by a beryllium reflector. This approach, generally speaking, gives a reactor that is more compact and of lighter weight than can be obtained with a moderated system having a softer neutron spectrum. In the reactor design, the path of heat flow is from the core to the inner reflector and then to the thermoelements in close contact with the inner reflector. The reject heat flowing from the thermoelement cold junctions enters the outer pontion of the reflector, which acts as the heat sink and conducts the reject heat to the large, circular, tapered-fin radiator which is attached to the reflector. Survey physics calculations …
Date: March 1, 1963
Creator: MacFarlane, D. R.
Object Type: Report
System: The UNT Digital Library
1000 Mwe Closed Cycle Water Reactor Study (open access)

1000 Mwe Closed Cycle Water Reactor Study

This report has two volumes, volume 1 contains the summary and detailed description of plant design, volume 2 contains a comprehensive nuclear evaluation of the reactor core.
Date: March 1, 1963
Creator: Westinghouse Electric Corp., Pittsburgh, Pa. Atomic Power Div.
Object Type: Report
System: The UNT Digital Library
1000 MWE Closed Cycle Water Reactor Study Volume II (open access)

1000 MWE Closed Cycle Water Reactor Study Volume II

This report includes the nuclear evaluation that has been conducted for the purpse of studying those problem areas which are expected to increase in severity as the core size is increased to produce 1000 MWE.
Date: March 1, 1963
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Adaptation of a Commercial Counter X-Ray Diffractometer for Investigations to 3000°C (open access)

Adaptation of a Commercial Counter X-Ray Diffractometer for Investigations to 3000°C

The rapid advances in many technologically important areas have not only served to accentuate the increased demands for high temperature metals and ceramics but have necessitated a more through knowledge of their physical properties when exposed to high temperature service. Toward this latter end, the use of X-ray diffraction has proved an invaluable tool in providing data of regions of thermal stability, expansion coefficients, solid solubility limits, and phase transformations by direct examination at temperature. Since this Laboratory has for some time now been engaged in the study of refractory nuclear materials, it was thought desirable to employ and possibly extend this technique to temperatures ranging up to 3000°C. This communication will describe the equipment developed for this purpose, with experimental results to be described in subsequent publications.
Date: March 12, 1963
Creator: LaPalca, Samuel; Farber, Gerald & Adler, George
Object Type: Report
System: The UNT Digital Library
Aeroradioactivity Survey and Areal Geology of the National Reactor Testing Station Area, Idaho (ARMS-I) (open access)

Aeroradioactivity Survey and Areal Geology of the National Reactor Testing Station Area, Idaho (ARMS-I)

Report regarding an airborne radioactivity survey that took place in the 10,000 square mile area surrounding the National Reactor Testing Station in Idaho Falls, Idaho. Topics include the types of bedrock noted in the area as well as their levels of radioactivity.
Date: March 1963
Creator: Bates, Robert G.
Object Type: Report
System: The UNT Digital Library
AN ALGOL 60 SYNTAX CHECKER FOR THE IBM 7090 COMPUTER (open access)

AN ALGOL 60 SYNTAX CHECKER FOR THE IBM 7090 COMPUTER

A syntax checker was designed based on the syntax of Algol as previously described. It was desirable to design the syntax checker as a set of mutually recursive processors tied together by building blocks which perform certain bookkeeping functions. Because of the recursive nature of the language and of the syntax checker, the problem of recovery after an error required much attention. A method was devised which permits most programs to be checked completely despite errors. The syntax checker was implemented for the IBM 7090 as a part of the SHARE ALGOL processor, and has operated very satisfactorily. (auth)
Date: March 21, 1963
Creator: Lietzke, M.P.
Object Type: Report
System: The UNT Digital Library
Alloying Characteristics of the Rare Earth Elements with the Transition Elements (open access)

Alloying Characteristics of the Rare Earth Elements with the Transition Elements

This report talks about the Alloying Characteristics of the Rare Earth Elements with the Transition Elements
Date: March 26, 1963
Creator: Sheeley, W. F.
Object Type: Report
System: The UNT Digital Library
Alternating Gradient Magnets (open access)

Alternating Gradient Magnets

The angle by which a magnet deflects the trajectory of a particle in the x-z plane is proportional to the integral [integral not transcribed] taken over the trajectory wherever B≠0. Alternating gradient focusing is achieved by designing magnets so that I=I(x) varies linearly with x over a suitable x interval. Usually this is done by shaping the poles to give a linear variation of By with x while keeping the length of the magnet constant for different x. Certain advantaged may be gained by varying the effective length of the magnet with x and keeping By constant so that the integral varies properly with x. Figure 1 shows several such poles for which the trajectory length, and hence the integral (1), varies approximately from 2/3 to 4/3 of the mean value.
Date: March 3, 1963
Creator: Beth, R. A.
Object Type: Report
System: The UNT Digital Library
Analog Computer Studies of the ML-1 Power Plant (open access)

Analog Computer Studies of the ML-1 Power Plant

From introduction: The main objective of the AGCRSP is to develop plans and specifications for a mobile nuclear power plant suitable for military field use.
Date: March 1963
Creator: Calamore, D. V.; Crimmins, D. H. & Tobey, E.
Object Type: Report
System: The UNT Digital Library
Annealing Studies on Irradiated Type 347 Stainless (open access)

Annealing Studies on Irradiated Type 347 Stainless

The effects of 1-hr anneals at 1000 and 1800 deg F on the mechanical properties of Type 347 stainless steel specimens taken from the ETR J-10 pressure tube after fastneutron (> 1 Mev) exposures of approximates 7.1 x 10/sup 21/ nvt were studied. The pressure tube operated at a maximum temperature of approximates 750 deg F in a stressed condition. Testing was done at 75 and 750 deg C. Uniform elongations were increased from approximates 1% in the as- irradiated material to 15 and 25%, respectively, by the 1000 and 1800 deg F anneals. The 1000 deg F annealing appeared to produce a better combination of mechanical properties. The microstructure of unirradiated, as-irradiated, and postirradiation-annealed specimens were very similar except for two specimens inadvertently heated above 1800 deg F during annealing. (auth)
Date: March 1, 1963
Creator: Murr, W. E. & Shober, F. R.
Object Type: Report
System: The UNT Digital Library
Annual Report of the Boy Scouts of America: 1962 (open access)

Annual Report of the Boy Scouts of America: 1962

Annual report submitted by the Boy Scouts of America to Congress describing highlights from 1962, activities, finance, service organizational leadership, and other information about scouting programs.
Date: March 21, 1963
Creator: Boy Scouts of America
Object Type: Report
System: The Portal to Texas History
Argonne Cancer Research Hospital Semiannual Report on Medical Research to the Atomic Energy Commission (open access)

Argonne Cancer Research Hospital Semiannual Report on Medical Research to the Atomic Energy Commission

Separate abstracts were prepared for 9 sections of this report. Five sections were previously abstracted and appeared in NSA. (C.H.)
Date: March 1, 1963
Creator: Jacobson, Leon O.
Object Type: Report
System: The UNT Digital Library
B high tank adequacy (open access)

B high tank adequacy

The pile power level curve, which includes data from PT 528 High Tank Drawdown Test and heat decay test, represents allowable power level for a given average High Tank temperature.
Date: March 22, 1963
Creator: Zimmerman, P. J.
Object Type: Report
System: The UNT Digital Library
BIO-ORGANIC CHEMISTRY QUARTERLY REPORT. December 1962 throughFebruary 1963 (open access)

BIO-ORGANIC CHEMISTRY QUARTERLY REPORT. December 1962 throughFebruary 1963

This report covers the following titles: (1) A versatile solvent to replace phenol for the paper chromatography of radioactive intermediary metabolites; (2) Chromatography of plant lipids on alumina paper; (3) Quinone and pigment composition of chloroplasts and quantasomes from Spinacea oleracea; (4) The lipid composition of chloroplast lamellae from Spinacea oleracea; (5) Metal chelates and photochemistry of flavins; (6) Photoinduced ESR in some solutions of organic electron donors and acceptors; (7) Fluorescence of oriented dye-macromolecule complexes--Theoretical study; (8) Formation of adenine by electron irradiation of methane, ammonia, and water; (9) Uptake of organic compounds by planarians; (10) The planaria: Absorption spectrum, cell disaggregation, and studies on homogenates.
Date: March 29, 1963
Creator: unknown
Object Type: Report
System: The UNT Digital Library
CARBIDE FUEL DEVELOPMENT. Phase IV Report, September 15, 1961-September 30, 1962 (open access)

CARBIDE FUEL DEVELOPMENT. Phase IV Report, September 15, 1961-September 30, 1962

Single-phase solid solution UC-- PuC powders were prepared by the carbon reduction of a mixture of UO/sub 2/ and PuO/sub 2/. A simple method was developed to determine the completion of the reaction by analyzing the exhaust gas from the furnace for CO. Four groups of solid solution (U/sub 0.8/Pu/sub 0.2/ )C/sub 0.95/ pellets were prepared for irradiation tests. The groups differed in the enrichment of uranium and in the presence or absence of nickel sintering aid. Without sintering aid, densities averaged about 92% of theoretical; with sintering aid the average density was about 96% of theoretical. The second phase, promoted by the use of nickel sintering aid, was identified as sesquicarbide. IRRADIATION TESTS. The post-irradiation examination of UC specimens irradiated to 16,400 Mwd/tonne (avg) at 1400 deg F and 9.6 kw./ft was completed. The effect of radiation on UC was slight: 0.001 in. diametral increase, 0.4% fission gas release, and no microstructural changes. The (U/sub 0.8/Pu/sub 0.2/)C/sub 0.95/ irradiation tests were redesigned for insertion in GETR. All the irradiation specimens were assembled, and assembly of the capsules was started. One fueled and one dummy capsule were shipped to the test site. (auth)
Date: March 31, 1963
Creator: Taylor, K.; Anderson, J. & Strasser, A.
Object Type: Report
System: The UNT Digital Library
Cell Population Kinetics of an Osteogenetic Tissue, I (open access)

Cell Population Kinetics of an Osteogenetic Tissue, I

Cell proliferation on the actively growing periosteal surface of the femur of rabbits aged two weeks, has been investigated using autoradiographic techniques. Injections of tritiated glycine and tritiated thymidine were given simultaneously and the animals sacrificed at intervals from one hour to 5 days after injection. The glycine labelled the position of the bone surface at the time of injection and the thymidine labelled the cells which were synthesizing DNA . The rate of increase in the cell population was determined by counting the number of cells beyond the glycine label at different times after injection. The cell kinetics of the fibroblast--pre-osteoblast--osteoblast--osteocyte system has been studied. The fibroblasts are relatively unimportant from the point of view of increase in the cell population. The main site of cell proliferation is the layer of preosteoblasts on the periosteal surface. The rate of movement of cells from the pre-osteoblast to the osteoblast and osteocyte compartments has been measured. The incorporation of osteoblasts into the bone is not a random process, but it appears that the osteoblast must spend a certain time on the periosteal surface before becoming either an osteocyte or a relatively inactive osteoblast lining a haversian canal. During its most active …
Date: March 12, 1963
Creator: Maureen, Owen
Object Type: Report
System: The UNT Digital Library
Cell Population Kinetics of an Osteogenetic Tissue, II (open access)

Cell Population Kinetics of an Osteogenetic Tissue, II

A study of the cell kinetics on the actively growing periosteal surface of the femur of rabbits ages two weeks has been continues. A single injection of tritiated thymidine was given and the rabbits killed from one hour to four days after injection. The grain count spectra of the different cell types, pre-osteoblast, osteoblast and osteocyte, have been compared at different times after injection. The results showed evidence for the uptake of thymidine in nuclei which is not associated with cell division. A small percentage of osteoblasts was initially labelled at one hour and there was evidence that the majority of these had not divided by 3 or 4 days after injection. Some thymidine labelled cells had also become osteocytes without division. Furthermore, it appeared that a considerable fraction of the initially labelled pre-osteoblasts did not divide. The S-period for the pre-osteoblasts and osteoblasts was measured using a double-labelled thymidine technique.
Date: March 12, 1963
Creator: Owen, Maureen & Pherson, Sheila Mac
Object Type: Report
System: The UNT Digital Library
Chemical Processing Department Monthly Report: February 1963 (open access)

Chemical Processing Department Monthly Report: February 1963

This report, for February 1963 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; weapons manufacturing operation; and safety and security.
Date: March 21, 1963
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Object Type: Report
System: The UNT Digital Library
Color Coding Orifices (open access)

Color Coding Orifices

An investigation was made to find a method of color coding the various jet orifices with different hole sizes to facilitate assembly of the NRX A-1 core. High temperature paints, ceramic paints, temperature indicating paints, and cements were investigated. Various degrees of success were obtained. No one type of paint was found which had excellent adherency after application and after being subjected to 1500°F for one-half hour, yet was available in many colors, was easy to apply and use, and had a very thin coat after drying. Some colors of high temperature paints will do as an alternate method to that of colored plastic caps presently planned.
Date: March 1, 1963
Creator: Parsons, L.E.
Object Type: Report
System: The UNT Digital Library
Comparison of Lumped and Distributed Inflector Magnets (open access)

Comparison of Lumped and Distributed Inflector Magnets

Desirable characteristics of pulsed magnets used as ejectors or inflectors for large accelerators can be obtained by loading the magnet with distributed capacitance or by using a capacitor in shunt with the load. Comparable field build-up tlmes are available with either arrangement. The lumped magnet system offers greater simplicity. (D.C.W.)
Date: March 18, 1963
Creator: Forsyth, E. B.
Object Type: Report
System: The UNT Digital Library
Consequences of a production reactor accident (open access)

Consequences of a production reactor accident

The purpose of this report is to estimate the consequences of a Hanford reactor accident with emphasis on the effects at distant points. The potential effects in Canada are estimated as well as the consequences within the United States.
Date: March 8, 1963
Creator: Junkins, R. L. & Watson, E. C.
Object Type: Report
System: The UNT Digital Library
CPD`s potential for processing the higher transuranics (open access)

CPD`s potential for processing the higher transuranics

Hanford`s potential has been evaluated for producing higher transuranic isotopes, particularly curium-242 and curium-244. This document outlines the concepts visualized, and estimates the potential impact on CPD`s development, construction, and production programs. The irradiation program would proceed in 3 steps: production of fuel-grade plutonium, its burning to higher isotopes and alloying with Al for use in one reactor, and the separated americium irradiated to form curium-242. Disposition of higher Pu isotopes and alternative production of curium-244 are discussed.
Date: March 14, 1963
Creator: Tomlinson, R. E.
Object Type: Report
System: The UNT Digital Library
The Cross Section, Volume 9, Number 10, March 1963 (open access)

The Cross Section, Volume 9, Number 10, March 1963

Monthly newsletter of the High Plains Underground Water Conservation District No. 1, discussing the field of underground water. Topics include profiles of water conservation research, annual pre-plant soil moisture survey data, annual Winter Water Level measurement data, and information about the latest water conservation tips.
Date: March 1963
Creator: High Plains Underground Water Conservation District No. 1 (Tex.)
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History
Crystalline Field Splittings in Holmium and Dysprosium Ethylsulfates (open access)

Crystalline Field Splittings in Holmium and Dysprosium Ethylsulfates

From report : "It has become apparent that pragmatic resonance data alone are insufficient to correctly evaluate crystal field parameters for rare-earth ethylsulfates, and that heat capacity data above 20°K are a useful aid in determining whether low lying levels obtained by absorption spectroscopy have been correctly identified."
Date: March 1963
Creator: Spedding, F. H.; Gerstein, B. C.; Haas, W. J.; Phillips, E. & Sutherland, W. L.
Object Type: Report
System: The UNT Digital Library