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Accidental Dispersion of Reactor Poisons and the Controlled Distance Required
Two types of hypothetical reactor catastrophe are considered. In the first of these, the Boiling Accident,'' it is assumed that a fraction of the radioactive material in a reactor is released to the atmosphere at a steady rate over a period of hours. In the second, the Puff Accident,'' it is assumed that the release of the radioactive material takes place instantaneously.'' The following concepts are used as measures of the hazard existing outside the controlled plant area. Danger Distance,'' defined as that distance beyond which the fission product cloud becomes so dilute that it cannot cause death; Probabiiity of Death per Capita per Accident,'' which is a measure of the hazard to any individual; and Expectation Number of Deaths per Accident.'' which is a statistical measure of the hazard to the entire off-site populace. Three mechanisms for each type of catastrophe were considered: direct irradiation from the fission product cloud, inhalation of the air in the cloud, and rainout from the cloud followed by irradiation from the ground. Failout is not considered. for it requires that a very energetic explosion be assumed. It is concluded that the size of the plant should be set by the hazard of irradiation …
Date:
March 1, 1958
Creator:
Menegus, R. L. & Ring, H. F.
Object Type:
Report
System:
The UNT Digital Library
HRP--PRELIMINARY STUDIES OF THE FLUIDIZED BED DENITRATION OF THORIUM NITRATE
S>Equipment for an exploratory study of the denitration of thorium nitrate in a fluidized bed was designed and constructed. Some operating difficulties were resolved and a successful initial run was made. (auth)
Date:
September 30, 1958
Creator:
List, H.L.
Object Type:
Report
System:
The UNT Digital Library
Diffusion in Metals. Progress Report and Publication List
Information concerning diffusion is presented, including a study of the relative rates of diffusion of Fe/sup 55/ and Fe/sup 59/ in Ag, diffusion of Ru in Ag, self-diffusion in AgCd and AgIn. chemical and tracer diffusion in Ag-alpha AgCd diffusion couples, the influence of pressure on diffusion in AgZn alloys, the energy of motion of vacancies in Au at high pressure, and ionic conductivity of alkali halides as a function of pressure and temperature. A list of publications containing diffusion information is also included. (J.R.D.)
Date:
May 15, 1958
Creator:
Seitz, F. & Lazarus, D.
Object Type:
Report
System:
The UNT Digital Library
ENGINEERING MATERIALS LIST. A Catalog of Drawings, Photographs, and Specifications Released by the United States Atomic Energy Commission. Supplement 1: SHIPPINGPORT PRESSURIZED WATER REACTOR
Unclassified Engineering Materials List, TM-4100(lst Rev.), is a catalog of available U. S. Atomic Energy Commission unclassified engineering drawing materials on the peaceful applications of atomic energy. The engineering literature described in this publication includes drawing, specifications, photographs, bill of materials, cost analysis, design criteria, psrts lists, and supporting textual data. This consolidated list m- cludes all materials originally announced in TM-4100, January 1957, and TID-4100, Supplement 1, July 1957, and additional engineering data received and cataloged by TlSE after the original issuances. The entire publication, TID-4100 lst Revision Supplement 1, is devoted to the Shippingport Pressurized Water Reactor. (W.L.H.)
Date:
May 1, 1958
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Some Cultural and Linguistic Aspects of the Garos
Book about the historical and social development of Garos over time focusing on religion and cultural practices with photographs and a short linguistic description of Garo including a list of cognates between Garo and Assamese with English glosses.
Date:
January 1958
Creator:
Choudhury, Bhupendranath N.
Object Type:
Book
System:
The UNT Digital Library
PROGRESS IN THE DEVELOPMENT OF A PROCESS FOR PRODUCING UO$sub 2$ PELLETS
Progress in the development of manufacturing procedures and techniques for uranium dioxide fuel pellets is described. Specifications for both the uranium oxide powder and the final fuel pellet are given. A process is described for making pellets wlth closely controlled density, dimensions, purity, and freedom from structural defects from ADU (ammonium diurante process) uranium dioxide powder. A formula relating lineaashrinkage to green and fired densitles has been derived, This formula has proven a useful tool in control of fired or slnterod pellet dimensions and densities esses described were utillzod in the manufacture of pellets for use in critical experiments. Improvements in processlng continue to be developed. (auth)
Date:
December 1, 1958
Creator:
Winchell, R.
Object Type:
Report
System:
The UNT Digital Library
Catalog of North Texas State College: 1958-1959, Undergraduate
Catalog for North Texas State College includes information about class offerings as well as general information about the school (academic calendar, list of officers and faculty, admissions and degree requirements, financial information, etc.).
Date:
February 1958
Creator:
North Texas State College
Object Type:
Book
System:
The UNT Digital Library
Report of the Forty-Third National Conference on Weights and Measures, 1958
Report of the annual conference on weights and measures, hosted by the U.S. National Bureau of Standards in Washington D.C. It includes conference proceedings, a list of attendees, information about committees and officers, and other reports or commentaries discussed at the meetings.
Date:
December 1, 1958
Creator:
United States. National Bureau of Standards.
Object Type:
Report
System:
The UNT Digital Library
Design of an Eddy-Current Brake for a Sodium-Cooled Nuclear Power Reactor
Two eddy-current electromagnets to act as brskes were designed and installed in the sodium-cooled nuclear pcwer reactor SRE to throttle sodium flow throughout the reactor after shutdown in order to maintain a constant reactor temperature gradient. One brake was used on the primary piping system, the other on the secondary system. It was determined that the eddy-current brake should cause a dragging pressure of 0.3 psi at a flow rate of 12 gal/min. The flux density necessary to produce this pressure was calculated, and the coil ampere- turns required to produce this fiux density were determined. Both brakes were controlled by thermocouples and performance was satisfactory. (M.C.G.)
Date:
July 10, 1958
Creator:
Baker, R. S.
Object Type:
Report
System:
The UNT Digital Library
Hazards Summary Report for the GCRE Critical-Assembly Experiments
Critical experiments are described, and the hazards attendant to these experiments are evaluated for a gascooled water-moderated reactor design. Shutdown control of the critical assembly is achieved by cadmium control blades and by dumping the water into a storage tank. The maximum normal rats of reactivity addition is limited to an estimated 0.04 per cent per sec for all remotely controlled operations. The system is interlocked to insure that safe operational procedures are followed, Hazard calculations are made to determine the dosage from direct radiation, fall-out, and inhalation from a radioactive cloud resulting from an accident. The exclusion area is shown to be adequate for even the maximum hypothetical accident. (auth)
Date:
July 22, 1958
Creator:
Hogan, William S.; Dingee, David A.; Jankowski, Francis J. & Chastain, Joel W.
Object Type:
Report
System:
The UNT Digital Library
Ultrasonic Fusion Joining of Sintered Aluminum Powder Materials to Aluminum Alloys
From abstract: "Essentially void-free fusion-type joints of high strength were produced between small specimens of Type M-276 sintered aluminum powder plate and 1100 Hl4 wrought plate, using a technique consisting of controlled and brief exposure of the ends of both materials to an ultrasonically active coupler face in a bath of molten 1100 aluminum, followed immediately by butt joining and fast cooling. With further development, the process should be adaptable to other types of sintered aluminum powder materials and to other joint geometries."
Date:
August 1958
Creator:
Thomas, John G. & Meyer, Florence R.
Object Type:
Report
System:
The UNT Digital Library
Graphite radiation damage as a reactor operational problem
Radiation Damage to the graphite moderator has played an important role in the history of reactor operation at Hanford. The operational problems, potential and real, which result from dimensional instability, stored energy, and gasification, as well as the solutions to these problems are discussed. The key to the graphite problems is operating temperature and its control. At present, stack expansion remains in the fringe regions of the original reactors, which coupled with the contraction of the central region gives rise to curvature problems in the top portion of the reactors. Stored energy is not a safety hazard because the release spectrum is such that a spontaneous and self sustained release cannot occur. Oxidation of the graphite moderator is controlled by maintaining operating temperature of the stack such that no significant amount of oxidation occurs.
Date:
April 14, 1958
Creator:
Curtiss, D. H.
Object Type:
Article
System:
The UNT Digital Library
Semiannual Report to the Atomic Energy Commission
Progress is reported in the following studies: the degradation of uric acid in man; the effect cf triiodothyronine on the oxidative metabolism of erythrocytes; the biosynthesis of abnormal proteins in multiple myeloma; tracer studies on the methbolism of DLglutamic acid in man; the effect of triiodothyronine on radiosensitivity of rats; the physiologic and clinical significance of erythropoietin; the measurement of isodose distributions from a revolving beam cobalt-60 therapy unit; tracer studies of protein binding and subcellular localization of digitoxin; applications of carbon-14 in methbolic studies; and tracer studies on the methbolism of progesterone. A list of publications during the period is included. (C.H.)
Date:
September 1, 1958
Creator:
Jacobson, Leon O. & Skozen, F. J.
Object Type:
Report
System:
The UNT Digital Library
Corrosion of AISI Type 304 Stainless Steel in High Temperature Borated Water
BS>The corrosion of type 304 stainless steel in water containing boric acid at 600 deg F and 2000 psig and at a flowvelocity of seven feet per second was investigated as a function of boron concentration and of alkaliknity. At a boron concentration of 39 ppm and at a pH value of 10, controlled with lithium hydroxide, no trend of corrosive attack with time was found after the first tw0 days. At a concentration of 41 ppm boron wlth no pH control (pH = 6.9), a regression tyoe equation of the form Y= A + B log (t), was found to express the relationship between corrosive attack and exposure teme. A similiar relationship was found at 1600 ppm boron withthe pH value maintained at 10 using lithium hydroxide. No evidence of raicrostructural attack was observed on coupon specimens under any of the conditions tested. The effects of surface finish and of position were studied. The effect of orientation of the rolling directon of coupon specimens with respect to the direction of fluid flow was also investigsted. (auth)
Date:
December 1, 1958
Creator:
Krieg, A. & Cytron, S. J.
Object Type:
Report
System:
The UNT Digital Library
Environmental Contamination From Weapon Tests
The program of the Atomic Energy Commission on environmental contamination from weapons tests is designed for the overall evaluation of the hazard to humans from test operations. It is limited to studies of the deposition of activity at long range rather than the problems associated with immediate, close-in fallout. The program has largely been a study of Sr{sup 90}, since considerations based on experience and measurement indicate that it is the isotope of greatest potential hazard. Data are presented pertinent to the monitoring of long-range fallout, particularly Sr{sup 90} and Cs{sup 137}. Values are tabulated for the fallout deposition, air concentrations, water concentrations, and the amounts in foods and human bone. In addition, results are given for some experimental investigations. The report of these results is not interpretative although certain papers that do attempt to interpret the present situation with respect to Sr{sup 90} in particular are reprinted. Bibliographies are presented covering the period since the 1957 hearings before the Joint Committee on Atomic Energy concerning the nature of radioactive fallout and its effects on man. A document list of submissions to the United Nations Scientific Committee on the Effects of Atomic Radiation is given to illustrate the work done …
Date:
October 1, 1958
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Geology of the Uranium Deposits of the Lukachukai Mountains Area Apache County, Arizona
Abstract: In a study of the comparative importance of sedimentary and tectonic ore controls and in search of data bearing on the origin of the deposits, ten mines in the Lukachukai Mountains, Apache County, Arizona were examined in detail. All commercial deposits in the area are in the Salt Wash Member of the Morrison Formation of Jurassic age. The ore bodies are elongate and horizontally lenticular in shape and consist of one or more ore pockets surrounded or separated by protore. The composite length of ore bodies consisting of two or more ore pockets separated by subore grade material ranges up to 1,100 feet; individual ore pockets range up to 350 feet in length. Elongation is usually at least three times the width and is parallel to paleostream depositional trends measured in and near the ore bodies. Claystone and/or siltstone units nearly always underlie and frequently overlie the host sandstone units. Ore occurs most frequently in trough-type, cross-stratified sandstone which fills scours and channels in the underlying claystone units. Lithofacies maps and mine mapping show that ore bodies are restricted to areas of rapid lateral color change which in general are also areas of rapid change in the ratio of …
Date:
September 1958
Creator:
Nestler, Ronald K. & Chenoweth, William L.
Object Type:
Report
System:
The UNT Digital Library
Progress Relating to Civilian Applications During January 1958
Data are given on: creep propenties of 15% coldworked Zircaloy-2; the liquidus in Al-U; effect of chloride on corrosion of type 304 ELC stainless steel; corrosion testing of stainless steels, Ti 75A lead, and rigid PVC as container materials for HNO/sub 3/-recovery process; viscosities of MgF/sub 2/ and MgF/sub 2/-MgO slags; phase boundaries in the U-Zr-H system; oxidation of Nb, Nb-W, and Nb-V alloys in dry air at 1000 and 1200 deg C; nonoxidizing properties of UO/sub 2/- La/sub 2/O/sub 3/ and UO/sub 2/-Sc/sub 2/O/sub 3/; study of bounding fuedamentals; hydrogen adsorotion by Nb; diffusion of H in ZrH/sub 4/; reflector controlled heterogeneous boiling reactor; pressure bonding of Zircaloy- 2-clad compartmented UO/sub 2/ fuel plates for PWR; and evaluation of UC as reactor fuel. (For preceding period see BMI-1247.) (T.R.H.)
Date:
February 1, 1958
Creator:
Dayton, R. W. & Tipton, C. R., Jr.
Object Type:
Report
System:
The UNT Digital Library
RADIOLOGICAL PHYSICS DIVISION SEMIANNUAL REPORT FOR JULY THROUGH DECEMBER 1957
Progress is reported in the following studies: effects of various doses of gamma radiation on the light absorbance of aerated and air-free samples of xylenes the design of a light piping system for a scintillation spectrometer; the development of a simple source of monoenergetic fast neutrons and the possibility of using a spherical moderator to produce a roughly monochromatic distribution of neutrons from a source of monochromatic neutrons of a higher energy; calculation of the body retention and elimination of Ra/sup 228/ and Ra/sup 224/ following a single injection of Th/sup 232/; the analysis of gamma-ray spectra by the method of least squares; application of a microradiographic technique in determinations of the mineral density of human bones at various ages and density values for old bone and new growth in bones from man, dogs, mice, cows, rabbits, and rats; the bone deposition of Ca/sup 45/ following injection in dogs; determination of the natural Ra/sup 226/ content of 200 water samples from Illinois municipal water supplies; attempts to estimate the fraction of the stratospheric Sr/sup 90/ in the total Sr/sup 90/ transported to the ground by rain by observing variations in the relative amounts of Sr/sup 89/, Sr/sup 90/, and Ba/sup …
Date:
February 1, 1958
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Army Package Power Reactor APPR-1 Operating Manual and Inspection and Service Manual
Report containing basic operating instructions for the operation of the Army Package Power Reactor. This includes descriptions of the the plant's systems, operations, and safety procedures.
Date:
February 1958
Creator:
Alco Products (Firm)
Object Type:
Report
System:
The UNT Digital Library
Operating Procedures and Emergency Plans for the Dresden Nuclear Power Station
The General Electric Company is designing and building a 180,000 kilowatt nuclear power plant for the Commonwealth Edison Company at a site 47 miles southwest of Chicago. The construction permit was issued on May 4, 1956 but is subject to submittal to the Commission of a final hazards summary report and a finding by the Commission that the final design provides reasonable assurances that the health and safety of the public will not be endangered by operation of the reactor in accordance with the specified procedures.
Date:
June 5, 1958
Creator:
Commonwealth Edison Company
Object Type:
Report
System:
The UNT Digital Library
Preliminary Design Report for the NMSR Pressurized Water Loop at ORR
The design criteria, description, flow diagrams, and some drawings of a pressurized water loop in which reactor operation conditions can be simulated are presented. The prirnary purpose of this test facility is irradiation testing of various versions of fuel elements for use in the Merchant Ship Reactor Program. The loop proper is designed for operation at 625 deg F and 2250 psi with a water flow rate of 90 gpm. Heat exchanger capacity is 150 kw at 300-F system water temperature. Loop construction is of 300 series stainless steels throughout. A by-pass purification system provides for continuous water chemistry control. Fuel pin specimens are to be irradiated in the space provided by two tubes, 1.5 II) x 24 in. long, of the "hairpin" type in positions A1 and A2 of the OHR core. The average unpertarbed neutron flux at this point in the reactor is estimated to be 5 x 10/sup 13/ thermal. (auth)
Date:
October 23, 1958
Creator:
Dudley, I.T.; Trauger, D.B. & Savage, H.W.
Object Type:
Report
System:
The UNT Digital Library
Preliminary Design: 22,000 SHP Boiling Water Reactor Marine Propulsion Plant for a Commercial Tanker
From abstract: "A preliminary design is presented for a boiling water reactor power plant for a propulsion of a 22,000 SHP commercial tanker."
Date:
December 1, 1958
Creator:
U.S. Atomic Energy Commission
Object Type:
Report
System:
The UNT Digital Library
100-Mw Nuclear Power Plant Utilizing a Sodium Cooled, Graphite Moderated Reactor
The conceptual design of a 100 Mw(e) nuclear power plant is described. The plant utilized a sodium-cooled graphite-moderated reactor with stainless- steel clad. slightiy enriched UO/sub 2/ fuel. The reactor is provided with three main coolant circuits, and the steam cycle has three stages of regenerative heating. The plant control system allows automatic operation over the range of 20 to 100% load, or manual operation at all loads. The site, reactor, sodium systems, reactor auxiliaries, fuel handling, instrumentation, turbine-generator, buildings. and safety measures are described. Engineering drawings are included. (W.D.M.)
Date:
February 28, 1958
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Liquid Metal Fuel Reactor Experiment Quarterly Technical Report: July - September 1958
Report containing research and development undertaken regarding the Liquid Metal Fuel Reactor Experiment.
Date:
October 1958
Creator:
Babcock & Wilcox Company
Object Type:
Report
System:
The UNT Digital Library