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Intermediate Heat Exchanger Preliminary Design. Vol. 1, IHX Preliminary Design

Description: Preface: The intermediate heat exchanger is designed for operation in a nuclear power plant using liquid sodium as the primary and secondary coolant. Since the primary fluid coming from the reactor is radioactive, the purpose of the IHX is to transfer heat to a nonradioactive fluid which then goes to a steam generator. Because of this activity the until will be enclosed in a concrete pit and will not be accessible during periods of operation. Immediately after shut down it will be necessary … more
Date: February 28, 1959
Creator: Alco Products (Firm)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Particle Extraction III

Description: A device to extend the operation of a beam extraction system is described for low energies where the radiation loss per turn is ineffective. The device consists of a noisy radiofrequency field which excites the radial betatron oscillation
Date: February 16, 1959
Creator: Robinson, Kenneth W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Rod Drop Transient. Test Results DL-S-247 (T-641323). Section I

Description: The purpose of the test was to obtain data on plant performance after a single rod has been dropped with the plant at 13 mw gross generator output. The operation of the plant after a single control rod (No. 23) had been dropped was within allowable limits. The high speed recorder charts could not be evaluated accurately due to the fast chart speed and also because they were calibrated to cover a much wider range than was necessary. The necessary data was obtained from the normal plant records i… more
Date: February 16, 1959
Creator: Price, F. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Yankee Atomic Electric Company Research and Development Program: Quarterly Progress Report: October 1, 1958 to December 31, 1958

Description: Quarterly report describing the technical research and development work accomplished by the Yankee Atomic Electric Company Research and Development Program, and documenting progress made on the group's various projects and goals.
Date: February 16, 1959
Creator: Garbe, R. W. & Walchli, H. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Decontamination Program Task II. Volume II, Evaluation of Chemical Agents for Nuclear Reactor Decontamination

Description: Abstract: The caustic permanganate-rinse decontamination treatment was investigated. Loop and metallurgical studies were performed to determine optimum operating conditions as well as the metallurgical effects of the treatment. A treatment with 10 percent sodium hydroxide and 5 percent potassium permanganate solution followed by a rinse with a 5 percent ammonium citrate, 2 percent citric acid and 1/2 percent Versene solution was chosen for the decontamination of a stainless steel steam generat… more
Date: February 15, 1959
Creator: Zegger, John L. & Pancer, Guyon P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactions of Metals with Oxygen and Steam. Final Report for June 15, 1958 - February 15, 1959

Description: Titanium, zirconium, and Zircaloy can spontaneously ignite under relatively mild conditions. The effect of temperature, oxygen concentration and pressure, and the nature of the diluent on the spontaneous ignition of titanium, zirconium, and Zircaloy were investigated.
Date: February 15, 1959
Creator: Littman, Fred E. & Church, Frank M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Decontamination Program Task II. Volume 1, Contamination and Decontamination in Nuclear Power Reactors

Description: Abstract: A survey of the problem of reactor system contamination by radioactive material and methods that have been employed to remove the material was carried out. Following this survey, an investigation of chemical solutions was undertaken to find one which might be successfully employed in the decontamination of a stainless steel steam generator. From a preliminary screening, the most promising chemical method from the view point of minimum corrosion and maximum decontamination is a caus… more
Date: February 13, 1959
Creator: Zegger, John L. & Pancer, Guyon P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Decontamination Program Task II. Volume III, Recommended Procedure for Decontamination of a Stainless Steel Steam Generator

Description: Abstract: A decontamination procedure for a stainless steel steam generator similar to the APPR-1 using a fill-flush application of a caustic permanganate-citrate combination solution is recommended. The isolation of the steam generator is to be accomplished by means of specially designed plugs at the reactor vessel outlet and at the primary coolant pumps. Anticipated results, including corrosion rates and decontamination factors, are presented.
Date: February 13, 1959
Creator: Pancer, Guyon P. & Zegger, John L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Control Rod Positions for Criticality. Section I. Third Performance. Test Results DL-S-149 (T-550130)

Description: The purpose of the test was to determine critical bank heights and bank worths for various rod configurations at normal plant operating temperature and pressure. The critical bank heights and bank worths were determined for various rod combinations are charted in the report.
Date: February 12, 1959
Creator: Baird, John B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Rod Drop Transient Test. Test Results DL-S-247 (T-641323). Section II

Description: The purpose of the test was to obtain data on plant performance after a single control rod has been dropped with the plant at 40 mw gross generator output. The operation of the plant after a single control rod (No. 23) had been dropped with within the allowable limits. The information obtained from the high speed recorders could not be evaluated accurately due to the fast chart speed and also because they were calibrated to cover a much wider range than was necessary. The necessary data was obt… more
Date: February 12, 1959
Creator: Heas, W. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Automatic Control and Load Swing Tests. Test Results DL-S-144 (T-554924). Section I

Description: The purpose of this test was to determine the controlling ability of the Reactor Power and Temperature Control System and to determine the operational characteristics of the station during load swings. The Reactor Power and Temperature Control System satisfactorily controlled rod movements to maintain all primary plant parameters within their individual limits during steady state operation, ramp functions load changes and a peak xenon burnout transient. The operational characteristics of the st… more
Date: February 10, 1959
Creator: Baird, John B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Station Output. Test Results DL-S-210 (T-612387). Section 1

Description: The purpose of the test was to obtain performance data at selected steady state generator loads. The data obtained during the performance of this test indicated that the station performed satisfactory under the new operating conditions of 500 F average coolant temperature and 1800 psia coolant pressure at the selected power lever of 57 mw.
Date: February 10, 1959
Creator: Cappola, M., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Determination of the Chemical Characteristics of the 1C Boiler. Test Results DL-S-209. Section III

Description: The purpose of the test was to determine the chemical operating characteristics of the 1C Boiler. The results of the tests performed on the 1C Boiler prior to the installation of new riser indicated that definite chemical hideout existed during full load operation of the boiler. Measurement of local concentrations further indicated that a stabilized steam picket existed in the upper region of the heat exchanger adjacent to the inlet tube sheet during high steaming rates. Since these test were p… more
Date: February 9, 1959
Creator: Kline, H. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Strain Cycling Tests of Large Specimens of AISI Type 347 Stainless Steel and 2-1/4 Croloy

Description: Twenty-one specimens one in. in diameter were tension-compression strain cycled to failure. Six specimens had transverse holes. Load-strain and load-time records were made. The unit strain ranges used were 0.026 and 0.09. The stainless steel specimens were tested at 662 F (350 C), the 2-1/4 Croloy specimens at 850 F. The cyclic life of a specimen with a hole can be predicated from smooth specimen tests by using the elastic stress concentration factor increased by 15%. In the commonly used expon… more
Date: February 9, 1959
Creator: Schnieder, A. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Scavenging of Particulate Matter in Connection with Nuclear-Powered Ships

Description: Gases, aerosols, and hydrosols are the forms of particulate matter which might be released from nuclear powered ships. Methods for scavenging these materials were studied in detail. Visual and radar techniques were used in tracking gases and aerosols in the free atmosphere. Scavenging of radioactivity dispersed in substitute ocean water by a permanganate-ferrous salt system was studied. A schematic diagram of a pneumatic conveying system for this type of scavenging material is provided.
Date: February 6, 1959
Creator: Rosinski, John
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Low-Energy [pi] Mesons in the Cosmic Radiation

Description: The intensity of 𝜋 mesons in the atmosphere is investigated in the energy region 𝐸kin≲50 Mev at sea level and at mountain altitudes. Positive 𝜋 mesons coming to rest in an absorber-scintillator are identified by the characteristic 𝜋−𝜇 decay. They are detected electronically and recorded photographically. The value 1.45±0.09 is adopted for the negative-to-positive ratio at small energies. The omnidirectional intensities 𝐽𝜋+ of slow positive 𝜋 mesons at sea level (91m), Echo Lake, Colorado (326… more
Date: February 2, 1959
Creator: Fotino, Mircea
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Chemistry and Nuclear Chemistry of the Heavy Elements : Progress Report No. 4

Description: This progress report covers the work on the project approximately between the dates June 1, 1058 and May 30, 1959, and is being submitted ahead of the contractual expiration date to support the request for renewal action. During the previous year work has continued to progress in the nuclear and inorganic sections of our heavy element group. The low-level counting equipment will make it possible to extend our fission studies to much lower energies. The U235 and U236 alpha induced fission is ess… more
Date: February 1959
Creator: Cobble, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Concentration of Plutonium by Cation Exchange -- Stabilization of Pu(Ill) in Nitric Acid

Description: Technical report. From Abstract : "Ascorbic and isoascorbic acids, used in conjunction with sulfamic acid, reduced Pu(IV) rapidly and completely to Pu(III) in solutions of nitric acid. The solutions of Pu(III) were stable. Aminoguanidine sulfate also retarded the oxidation of Pu(III) but did not reduce Pu(IV)."
Date: February 1959
Creator: Tober, Frank W., 1919-1995 & Russell, Edwin R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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