Design and Feasibility Study of a Pebble Bed Reactor-Steam Power Plant (open access)

Design and Feasibility Study of a Pebble Bed Reactor-Steam Power Plant

The status of development studies being conducted on a pebble bed power reactor is outlined. The items discussed are fuel element manufacture, stability, and reprocessing, and component development. (D.L.C.)
Date: May 1, 1958
Creator: unknown
Object Type: Report
System: The UNT Digital Library
LITERATURE SEARCH ON LEAD-BISMUTH ALLOYS (open access)

LITERATURE SEARCH ON LEAD-BISMUTH ALLOYS

BS>The use of a lead-bismuth alloy as a coolant in the removal of heat from power-generating nuclear reactors was considered with the possibility that its ternary alloy with uranium or plutonium might be of use in a reactor of the circulating-liquid-fuel type. Information collected from the literature covering phase-equilibrium studies, physicalproperty data, and reactivity of this alloy toward other substances is presented. (auth)
Date: February 14, 1950
Creator: Lee, M.E.
Object Type: Report
System: The UNT Digital Library
CIVILIAN POWER REACTOR PROGRAM. PART III. CORE-PARAMETER STUDIES FOR SELECTED REACTOR TYPES (open access)

CIVILIAN POWER REACTOR PROGRAM. PART III. CORE-PARAMETER STUDIES FOR SELECTED REACTOR TYPES

A report is presented to provide a tool for evaluating the relative economic incentives for changing reactor core parameters. The cost relations are shown in terms of differential cost in lieu of total cost. A total cost for each reactor described is included so that power costs for a specified set of parameters can be obtained. A description is also included concerning 5 reactor types considered along with a discussion of the effects on power costs of varying the significant core parameters. A listing of basic references is given. (J.R.D.)
Date: January 1, 1959
Creator: Atomic Energy Commission, Washington, D.C. & Jackson and Moreland, Inc., Boston
Object Type: Report
System: The UNT Digital Library
Hanford Laboratories Operation monthly activities report, March 1959 (open access)

Hanford Laboratories Operation monthly activities report, March 1959

This document details activities of the Hanford Laboratories Operation during the month of March 1959. (FI)
Date: April 15, 1959
Creator: unknown
Object Type: Report
System: The UNT Digital Library
SRE CONTROL ROD SHIELDING REQUIREMENTS (open access)

SRE CONTROL ROD SHIELDING REQUIREMENTS

Data taken on radiation traverse of the Mark 1 control rod were analyzed. Future radiation levels for all SRE control and safety rods were predicted from this. The shielding necessary to ship a complete rod and that necessary to protect a person doing maintenance work on these rods were calculated. The unshielded gamma dose rate 1 cm from the surface of the most highly activated portion of the control rod was calculated to be 5.0 x 10/sup 4/ r/hr 14 days after shutdown following an extended power run of 90 days duration. (M.C.G.)
Date: October 22, 1957
Creator: Whittum, H.O.
Object Type: Report
System: The UNT Digital Library
Creep Rupture in the Presence of a Fast Neutron Flux (open access)

Creep Rupture in the Presence of a Fast Neutron Flux

Possible mechanisms for creep rupture during irradiation are examined. Evidence that the rupture occurs by grain boundary sliding alone, or by vacancy condensation, is compared. It is observed that vacancy condensation is the more probable mechanism, and that this mechanism predicts a reduction in creep rupture life for metals exposed to a fast neutron flux (neglecting effects of radiation annealing). (T.F.H.)
Date: January 14, 1959
Creator: Gregory, D. P.
Object Type: Report
System: The UNT Digital Library
Advanced energy sources and conversion techniques. Volume 1. [35 papers] (open access)

Advanced energy sources and conversion techniques. Volume 1. [35 papers]

This report addresses the advanced energy sources and conversion techniques.
Date: November 1, 1958
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Production of Pebble-Type Fuel Elements (open access)

Production of Pebble-Type Fuel Elements

A capillary-drop method of producing spherical shapes of brittle materials less than 0.l00 inch in diameter was developed. It appears to be a feasible means for producing large numbers of pebble-tyne fuel element cores. Coating of pebble-type fuel element cores by the coating-pan technique, though not adequately developed, showed promise. (auth)
Date: June 1, 1955
Creator: Brassfield, H.C.
Object Type: Report
System: The UNT Digital Library
GCRE-I HAZARD SUMMARY REPORT (open access)

GCRE-I HAZARD SUMMARY REPORT

The GCRE-I hazard summary report is supplemented in the following areas: geometry and operation of the steam cooling system, the reactor coolant by-pass, and by-pass valving; the means by which by-passed circuits are prevented from remaining unintentionally disabled; design details, and details of procedure for core flooding operations. (A.C.)
Date: March 1, 1959
Creator: unknown
Object Type: Report
System: The UNT Digital Library
REACTOR FUEL WASTE DISPOSAL PROJECT PRESSURE-TEMPERATURE EFFECT ON SALT CAVITIES AND SURVEY OF LIQUEFIED PETROLEUM GAS STORAGE (open access)

REACTOR FUEL WASTE DISPOSAL PROJECT PRESSURE-TEMPERATURE EFFECT ON SALT CAVITIES AND SURVEY OF LIQUEFIED PETROLEUM GAS STORAGE

It is deemed feasible to store reactor fuel wastes in a salt dome cavity to a depth where the differential in pressure between the soil over-burden pressure and pressure of the fluid inside the cavity does not exceed 3000 psi, and the temperature is less than 400 deg F. Tests at pressure increments of 1000 psi were conducted on a 2" cylindrical cavity contained in a 6-in. long by 6-in. cylindrical salt core. Tests indicate that the cavity exhibited complete stability under pressures to 3000 psi and temperatures to 300 deg F. At temperatures of 100 to 400 deg F and pressures to 5000 psi continuous deformation of the cavity resulted. Initial movement of the salt was observed at all pressures. This was evidenced by vertical deformation and cavity size reduction. It was noted that a point of structural equilibrium was reached at lower temperatures when the pressure did not exceed 5000 psi. A literature study reveals that the most common type of cavity utilized in liquefied petroleum gas storage is either cylindrical or ellipsoidal. A few are pear or inverted cone shaped. There was no indication of leakage for cavities when pressure tested for as long as 72 hr. …
Date: January 15, 1959
Creator: Brown, K. E.; Jessen, F. W. & Gloyna, E. F.
Object Type: Report
System: The UNT Digital Library
Effects of Overpressures in Group Shelters on Animals and Dummies (open access)

Effects of Overpressures in Group Shelters on Animals and Dummies

S>Relative biological hazards of blast were studied in two types of communal air-raid shelters during Shots 1 and 8. Dogs, restrained within the shelters during detonation, were studied pathologically and clinically for blast injuries. Two anthropometric dummies were test objects for displacement studies utilizing high-speed photography. Physical data included pressure vs time and air-drag determinations. During Shot 1, animals sustained marked blast damages (hemorrhages in lungs and abdominal organs), three dogs were ataxic. and the dummies were rather violently displaced. In Shot 8, however, no significant injuries were found in the animals, and the dummies were minimally displaced. Analysis of the physical data indicated that blast injuries and violent displacements may occur at much lower static overpressures than previously assumed from conventional explosion data. Furthermore, biological damage appeared to be related to the rate of rise of the overpressure and air drag, as well as the maximum overpressure values. (auth)
Date: September 1, 1953
Creator: Roberts, J. E.; White, C. S. & Chiffelle, T. L.
Object Type: Report
System: The UNT Digital Library
RADIATION CREEP (open access)

RADIATION CREEP

Several theories of metal creep and radiation damage are studied, in order to determine whether creep rates under various conditions of irradiation can be predicted theoretically. It is found that if the creep is of the recovery type, and if the diffusion coefficient for radiationinduced vacancies is large enough, creep rates may be increased within a limited temperature range. Otherwise, radiation has no effect on creep rates. (T.F.H.)
Date: December 1, 1957
Creator: Gregory, D.P.
Object Type: Report
System: The UNT Digital Library
THE ELECTROMAGNETIC PINCH EFFECT FOR SPACE PROPULSION (open access)

THE ELECTROMAGNETIC PINCH EFFECT FOR SPACE PROPULSION

The phenomenon of the electromagnetic pinch effect is used to accelerate ionized gases for space propulsion. Electrical energy, initially stored in capacitors, is discharged across two nozzle shaped electrodes wherein the radial pinch is converted to axial motion of the effected gases instead of confinement at the axis. The gas dynamics of a pinch using the hydrodynamical model of a msgnetic piston driving a shock wave is combined with the electrodynamics of the circuit to calculate the discharge behavior. Experiments on three different electrode designs are discussed and results compared with calculated values. Results are applied to one particular space propulsion system consisting of a nuclear energy source, a space radiator, a turbine-generator, capacitor, and a pinch tube. The specific mission analyzed is a one-way unmanned flight to a Mars orbit, starting from an Earth orbit. (auth)
Date: August 1, 1959
Creator: Kunen, A.E. & McIlroy, W.
Object Type: Report
System: The UNT Digital Library
RECONNAISSANCE FOR URANIUM IN THE CUZCO-AYAVIRI REGION, SOUTHERN PERU (open access)

RECONNAISSANCE FOR URANIUM IN THE CUZCO-AYAVIRI REGION, SOUTHERN PERU

Geologic and radiometric investigations of the CuzcoAyaviri region in southern Peru were made in a search for geologic features or structures which might be favorable for the occurrence of uranium. Outcrops consist of Lower Paleozoic sedimentary and metamorphic rocks; Permian to Carboniferous volcanic flows, tuffs, breccia and agglomerate, together with sedimentary rocks; and Cretaceous and sedimentary rocks. Cretaceous to Tertiary igneous rocks are acidic intrusives and extrusive rhyolite, dacite and trachyte. Tertiary to Quaternary volcanic tuffs, breccias and agglomerates are also present. Although no anomalous radioactivity was observed, favorable geologic features for the occurrence of uranium were noted at two localities. (auth)
Date: October 1, 1957
Creator: Brown, L.J. & Francisco, C.L.
Object Type: Report
System: The UNT Digital Library
Atmospheric Signals From Explosions and Their Interpretation (open access)

Atmospheric Signals From Explosions and Their Interpretation

Results are reported from a series of experimental highexplosive shots under inversion conditions at the Nevada Test Site which were made in an attempt to refine blast prediction techniques. Applications of the data in determinations of the amount of energy which remains in the blast wave as it reaches acoustic level and in determinations of the magnitude of the reflection factor when the blast wave strikes the ground are discussed. Data on shock wave propagation are presented graphically. It is concluded that the blast phenomenology of high-altitude shots can be predicted by using modified Sach's scaling. With some extrapolation to the height-of-burst versus blast-yield curve, it should be possible to make order-of-magnitude predictions of blast effects from high-altitude shots up to heights of burst of 1,000,000 ft. (C.H.)
Date: December 1, 1959
Creator: Reed, J. W.
Object Type: Report
System: The UNT Digital Library
AIRBLAST OVERPRESSURE AND DYNAMIC PRESSURE OVER VARIOUS SURFACES (open access)

AIRBLAST OVERPRESSURE AND DYNAMIC PRESSURE OVER VARIOUS SURFACES

Static overpressure and dynamic pressure versus time over surfaces processing different physical properties were measured on two tower shots, 6 and 12. On Shot 12, three surfaces were provided: the natural desert, a water surface consisting of a flooded area, and an asphalt surface. On Shot 6, desert and asphalt areas only were available. There were 123 channels of instrumentation installed for Shot 12, and 24 for Shot 6. From the data, a system of wave-form classification was devised for overpressure and dynamic-pressure- versus-time measurements. Incorporation of this system into data analysios indicates that it is possible for an ideal peak pressure to be identified with a nonideal wave form. Introducing both variables, wave form and peak pressure, into analyses reduces ambiguioties associoated with comparing results of different nuclear tests. The data show the effect of the nature of the surface upon airblast phenomena from a nuclear explosion. The effects of surface conditions upon shock phenomena are made more understandable by a review of temperature computatioons, using shock wave parameters in addition to an analysis based upon the arrioval time of the thermal pulse. A phenomenological discussion of precursor formation is presented, and comparisons are made using data from all …
Date: September 11, 1957
Creator: Sachs, D. C.; Swift, L. M. & Sauer, F. M.
Object Type: Report
System: The UNT Digital Library
RELEASE OF FISSION GASES FROM THE AE-6 REACTOR ON MARCH 25, 1959 (open access)

RELEASE OF FISSION GASES FROM THE AE-6 REACTOR ON MARCH 25, 1959

An analysis was made of the fission-gas-release incident during the pressure pumpdown of the AE-6 Reactor resulting in the contamination of the reactor room and members of the operating staff. Descriptions are given of the normal core pumping procedures, procedural alterations during the incident, the discovery of the contamination and its possible causes, and the remedial actions taken. Steps taken to minimize the chance of the occurrence of the contamination in the future are listed. (B.O.G.)
Date: April 15, 1959
Creator: Blackshaw, G.L.
Object Type: Report
System: The UNT Digital Library
FLUX DISTRIBUTIONS AND LEAKAGE CURRENTS FOR SRE, P-16 (open access)

FLUX DISTRIBUTIONS AND LEAKAGE CURRENTS FOR SRE, P-16

BS>Two-group, two-region criticality calculations were made for 10 and 11 ft diameter tanks. The 10 ft tank required a core radius of 102 cm and the 11 ft tank a core radius of 95 cm for criticality. In the calculations, the fluxes were assumed to go to zero at the edge oi the graphite reflector. The fast group of the two-group calculation was broken down into 3 fast groups. The leakage out of the core and reflector for the 4 energy groups is given. (M.C.G.)
Date: January 29, 1954
Creator: Balent, R.
Object Type: Report
System: The UNT Digital Library
HAZARDS SUMMARY REPORT ON NUCLEAR PHYSICS LABORATORY AT CANEL (open access)

HAZARDS SUMMARY REPORT ON NUCLEAR PHYSICS LABORATORY AT CANEL

ON NUCLEAR PHYSICS LABORATORY AT CANEL. The critical experiment facility at CANEL is described. Information of the mature of experimental assemblies and operations is included. Safety features of the building, equipment, and operations are pointed out. Possible accidents and the resulting hazards to surrounding areas are analyzed. The make-up of the surrounding area is described. (M.C.G.)
Date: October 13, 1955
Creator: unknown
Object Type: Report
System: The UNT Digital Library
RECONNAISSANCE FOR URANIUM IN THE PROVINCES OF AYABACA AND HUANCA-BAMBA, DEPARTMENT OF PIURA, PERU (open access)

RECONNAISSANCE FOR URANIUM IN THE PROVINCES OF AYABACA AND HUANCA-BAMBA, DEPARTMENT OF PIURA, PERU

In 1957 a radiometric examination of rock outcrops in the Ayabaca and Huancabamba areas of northwestern Peru was made in conjunction with a geologic search for structures favorable for the occurrence of uranium minerals. No anomalous radioactivity was detected, and the geologic setting is believed to be generally unfavorable for uranium mineralization. (auth)
Date: September 1, 1957
Creator: Brown, L.J. & G.S., Morales
Object Type: Report
System: The UNT Digital Library
U.S. NAVY STRUCTURES. ANNEX 3.2 OF SCIENTIFIC DIRECTOR'S REPORT OF ATOMIC WEAPON TESTS AT ENIWETOK, 1951 (open access)

U.S. NAVY STRUCTURES. ANNEX 3.2 OF SCIENTIFIC DIRECTOR'S REPORT OF ATOMIC WEAPON TESTS AT ENIWETOK, 1951

Structures are subjected to a 50-kt blast, in order to obtain fundamental data on structures subjected to blast loading, to observe the response of the structures under this loading, and to determine the relative blast-resistance merits of several structural types. Modes of failure are determined. Shaped structures are found to be superdor to rectangular structures. Earth cover for the structures is also found to increase the blast resistance. It is found that standard Navy heavy bomb-proof structures with modifications can withstand a near-surface atomic burst at ground zero. (T.F.H.)
Date: June 1, 1952
Creator: Hayen, C.L.
Object Type: Report
System: The UNT Digital Library
Survey of Nonmetallic Liquid Coolants for Nuclear-Power Piles (open access)

Survey of Nonmetallic Liquid Coolants for Nuclear-Power Piles

A comprehensive survey of the literature was made in an effort to identify nonmetallic materials of possible usefulness as liquid coolants. Materials having maximum melting points of 1000 deg F and boiling points of l200 deg F were considered, but boiling points above 2200 deg F were preferred. Melting points, boiling points, densities, heat capacities, and thermal conductivities were tabulated. Approximately 190 materials appeared to have melting and boiling temperatures in a suitable range. A paucity of thermal- conductivty and heat-capacity data prevented further estimates of suitability of all but nine of these materials. Of these nine nonmetallics, only sodium hydroxide appeared to offer possibilities when considered according to the NEPA formula. (M.C.G.)
Date: May 26, 1950
Creator: Shaw, H.L. & Boulger, F.W.
Object Type: Report
System: The UNT Digital Library
Steady State Thermal Behavior of Hnpf Sodium Heat Transfer System (open access)

Steady State Thermal Behavior of Hnpf Sodium Heat Transfer System

The performance of the Hallam Nuclear Power Facility heat transfer components was investigated in order to determine the steady-state, part load characteristics under various operating conditions. The complete steady-state temperature distributions, variations of flow rates and heat transfer coefficients throughout the sodium heat transfer systems as functions of reactor load are shown in a series of graphs. (M.C.G.)
Date: August 10, 1959
Creator: Stell, A.T.
Object Type: Report
System: The UNT Digital Library
Sodium Graphite Reactor. Quarterly Progress Report, July-September 1954 (open access)

Sodium Graphite Reactor. Quarterly Progress Report, July-September 1954

Technology of the Sodium Graphite Reactor. Reactivity calculations were made to study the application of steadystate plutonium feedback techniques to the use of diffusion plant tails for reactor fuel feed material. The performance and design of a twin core SGR power plant are given. Thermal neutron flux distribution measurements are reported for a six-rod fuel cluster and for a hollow uranium rod. A power cost calculation was made for a 1000-Mw SGR Th-U/sup 233/ breeder reactor which starts up on Th--U/sup 235/ alloy. Calculations were made on neutron leakage through the SRE shield. Research on reactor fuel elements and reactor materials are described. Corrosion and irradiation damage data at 5 x 10/sup 7/ r dose (150 deg F) on toluene as the SRE shield coolant indicate that the radioinduced corrosion of Fe, Al, and Cu in the SRE shield should be negligible. Preliminary results are summarized for l-Mev electron ir radiation studies of terphenyls at 400 to 450 deg C. Sodium Reactor Experiment. Progress is reported for various portions of the SRE project: reactor design and evaluation, fuel elements, moderator, reflector, structure, reactor cooling and heat transfer, instrumentation and control, shielding, and reactor services. (D.L.C.)
Date: December 1, 1954
Creator: Siegel, S. & Inman, G.M. eds.
Object Type: Report
System: The UNT Digital Library