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Research and Development Reports for Sodium to Sodium Intermediate Heat Exchanger and Sodium to Water Steam Generator

Description: Results are presented of research and development work performed in conjunction with the 70-Mw design of a sodium-to- sodium intermediate heat exchanger and a sodium-to-water steam generator. Kanigen plating was substituted for Inconel overlays. A program to evaluate this plating was undertaken. Elimination of tube end ferrules, mechanical behavior of sine wave tubes, tube-to- tube sheet welded connections, metallurgical examination of bimetallic tubes, transition weld test, bayonet tube test, … more
Date: October 30, 1960
Partner: UNT Libraries Government Documents Department
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REACTOR FUEL WASTE DISPOSAL PROJECT-PERMEABILITY OF ROCK SALT AND CREEP OF UNDERGROUND SALT CAVITIES. Final Report

Description: A study was made of two problems of salt-cavity storage, namely, seepage of wastes out of formations and closure of cavities due to plastic flow of salt. The results indicate that both problems are negligible; bedded salt is more impermeable than dome salt. Kerosene was found to be nonreactive with dome salt whereas brine solutions showed some interaction. It is concluded that storage of radioactive wastes in salt cavities is feasible. (D.L.C.)
Date: December 30, 1960
Creator: Reynolds, T.D. & Gloyna, E.F.
Partner: UNT Libraries Government Documents Department
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MARITIME GAS-COOLED REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING, SEPTEMBER 30, 1960

Description: The feasibility was studied and a cost estimate prepared of an experimental reactor to determine the operating characteristics of beryllia- moderated, gas-cooled systems wtthin a power limit of 10 Mw(t). The heat energy produced by the experimental reactor is to be dissipated in a heat dump. No machinery for production of power was to be provided. Other requirements were that the reactor should be capable of testing core types different from the current MGCR design, and the system should permit… more
Date: September 30, 1960
Partner: UNT Libraries Government Documents Department
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PT-IP-385-C, E-N reactivity matching measurement

Description: The projected E-N load at H Reactor will require a complete change in the type of charge placed in most flattened zone process tubes. Objective of this test is to determine the reactivity of the proposed E-N charge relative to the known natural uranium charge reactivity.
Date: December 30, 1960
Creator: Carter, R. D.
Partner: UNT Libraries Government Documents Department
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P-V-T Relationships of BF₃ Gas

Description: Abstract: A generalized equation of state developed by Gouq-Jen Su and Chien-Hou Chang is used for predicting P-V-T behavior of BF3 at high gas densities.
Date: July 30, 1960
Creator: Smith, C. R. F.
Partner: UNT Libraries Government Documents Department
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Valve Stem Freeze Seal for High-Temperature Sodium

Description: Abstract: An experimental study of valve stem freeze seals was undertaken as part of the effort to develop components for high temperature service in advanced sodium-cooled reactor systems.
Date: July 30, 1960
Creator: McDonald, J. S.
Partner: UNT Libraries Government Documents Department
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Production test IP-333-D, Supplement A: Irradiation of two defected UO{sub 2} fuel element assemblies

Description: To permit either the irradiation of two defected UO{sub 2} four-rod-cluster fuel element assemblies during the same operating period, or the irradiation of the two assemblies singly during two different operating periods in KE Reactor front-to-rear test hole 3865. The density of UO{sub 2} in one fuel element assembly is 90% of theoretical, in the other 87%. In both assemblies the fuel element cladding is Zircaloy and the fuel material natural uranium. An artificial defect will be made in each a… more
Date: November 30, 1960
Creator: Marshall, R. K.
Partner: UNT Libraries Government Documents Department
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OMR (Piqua) Unitized Control-Safety Rod Prototype Tests

Description: Abstract: A unitized magnetic jack driven control-safety rod has been developed for the 45.5 thermal megawatt organic moderated reactor (Piqua).
Date: June 30, 1960
Creator: Howell, J. D. & Weeks, C. C.
Partner: UNT Libraries Government Documents Department
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High Temperature Corrosion of Some Metals and Ceramics in Fluorinating Atmospheres

Description: Abstract: The results of this investigation leave little doubt that diffusion of the fluorinating gas along the grain boundaries of the nickel fluoride film to react at the metal-scale interface is the primary mechanism of attack upon pure nickel and its more promising alloys.
Date: September 30, 1960
Creator: Hale, C. F.; Barber, E. J.; Bernhardt, H. A. & Rapp, Karl E.
Partner: UNT Libraries Government Documents Department
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NS Savannah Nuclear Merchant Ship Design Review. Summary Report

Description: Results of a survey covering the safety, adequacy, and reliability of certain design and construction features pertaining to the NS Savannah nuclear power plant and related systems are presented. (auth)
Date: June 30, 1960
Partner: UNT Libraries Government Documents Department
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THERMAL CYCLING TESTS ON U-10 w/o Mo FOR THE ORNL FAST BURST REACTOR

Description: One of the uncertainties concerning the use of uranium-10 wt.% molybdenum in the ORNL Fast Burst Reactor is the thermal-cycling behavior of this alloy. Accordingly, an experimental program was undertaken to determine whether transformation or distortion of gamma-phase uranium--10 wt.% molybdenum can occur during simulated fast-burstreactor thermal cycling, and, should transformation occur, to establish the thermal cycling behavior of partially transformed uranium- - 10 wt.% molybdenum. Specimen… more
Date: July 30, 1960
Creator: Minushkin, B.
Partner: UNT Libraries Government Documents Department
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Final Safety Analysis Report: SNAP 1A Radioisotope Fueled Themonuclear Generator

Description: The following report is the final safety analysis report for the Task 2 Radioisotope Powered Thermoelectric Generator prepared by The Martin Company. It presents analyses, tests and evaluation of the operational safety criteria for the generator.
Date: June 30, 1960
Creator: Dix, George P.
Partner: UNT Libraries Government Documents Department
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Application of Nuclear Power Supplies to Space Systems

Description: Studies were made to ascertain what useful satellite and/ or space missions may be accomplished with the SNAP 2, 8, and 10 power systems within the 1960 to 1970 time period, to delineate useful satellite and/or space missions which would most profitably employ nuclear power sources, to ascertain what restrictions are imposed on various payloads as a result of having a nuclear power system on board, and to investigate the general vehicle integration and installation requirements of the SNAP 2 an… more
Date: June 30, 1960
Partner: UNT Libraries Government Documents Department
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Process summary of Purex Plant operation, January 1961--December 1961

Description: This report describes Purex Plant operations at Hanford for January, 1961-- December, 1961. Solvent extraction and ion exchange processes and data are discussed.
Date: December 30, 1960
Creator: Geier, R. G. & Rathvon, H. C.
Partner: UNT Libraries Government Documents Department
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ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM SUMMARY REPORT ON MATERIALS FOR THE GCRE-II

Description: Investigatiors were made of various materials for development of metal- canned and semi-homogeneous GCRE-II fuel element concepts. The materials were studied for application to development of fuels, grapanite, silicon-silicon carbide coatings, metal claddings, carburization barrier coatings, and graphite joining. A survey of the literature showad that uranium carbide fuels are superior to other types for the applications described and that refractory metal or metal carbide fuel coatings appear … more
Date: December 30, 1960
Creator: Carpenter, R. & Del Grosso, A.
Partner: UNT Libraries Government Documents Department
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FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. A Topical Report on SUB-SURFACE COATINGS FOR FUELED GRAPHITE SPHERES

Description: An exploratory program on subsurface coatin8s for graphite fuel elements is summarized. A number of coatings with various melting points which could be located beneath the surface of a fueled graphite sphere were investigated. Of the materials with lower melting points. nickel and a special glass compound appeared to form continuous coatings when a hot-pressing technique was employed. Several materials with high melting points. such as Ti, Cr, and MoSi/sub 2/, showed some promise, even though p… more
Date: June 30, 1960
Partner: UNT Libraries Government Documents Department
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Valve Stem Freeze Seal for High-Temperature Sodium

Description: Valve stem freeze seals for high-temperature service in advanced sodium- cooled reactor systems were studied. An experimental model, suitable for use with a 6-in. size valve, operated satisfactorily under a variety of conditions. The freeze seal region was cooled by natural convection to ambient atmosphere; cooling by both circumferential and longitudinal finned sections was experimentally studied. The operating conditions included sodium bulk temperatures up to 1300 tained F, sodium pressures … more
Date: July 30, 1960
Creator: McDonald, J.S.
Partner: UNT Libraries Government Documents Department
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THERMODYNAMIC PROPERTIES OF GASEOUS URANIUM HEXAFLUORIDE

Description: Tables of temperature dependent coefficients are presented for the computation of thermodynamic properties of gaseous UF/sub 6/ using equations which express the properties as expansions in powers of pressure. The various coefficients listed were computed in one degree increments for a temperature range of 500 to 999 deg R. This set of tables was computed by use of a virial equation representation for the equation of state and the thermodynamic properties were derived from this representation. … more
Date: September 30, 1960
Creator: Parks, B.H. & Burton, D.W.
Partner: UNT Libraries Government Documents Department
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Engineering Evaluation of Volatility Pilot Plant Equipment

Description: The operation of the ORNL Volatility Pilot Plant for decontaminating and recovering uranium from molten-salt reactor fuels is discussed. A description of equipment, operating details, and performance of each system within the plant is contained. (C.J.G.)
Date: September 30, 1960
Creator: Miles, F W & Carr, W H
Partner: UNT Libraries Government Documents Department
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