Technical basis for establishing process tube pressure limits for KER loops 2 and 3 and for the NPR Prototype Facility (open access)

Technical basis for establishing process tube pressure limits for KER loops 2 and 3 and for the NPR Prototype Facility

In compliance with a request from Coolant Testing Operation, the Reactor Engineering Operation has made a study to determine the maximum operating pressure limits for the pertinent Zircaloy-2 process tubes. Since these tubes shall be used for testing NPR fuel elements, it is considered desirable that KER Loops 2 and 3 permit operation at temperatures of around 300{degrees}C while the NPR prototype facility permit operation at about 316{degrees}C in a manner such that there is minimum hazard to the KE-Reactor and to personnel.
Date: June 26, 1959
Creator: Adams, O. E.
Object Type: Report
System: The UNT Digital Library
Acenaphthene solvents for use in Building 313 Frost Test operation (open access)

Acenaphthene solvents for use in Building 313 Frost Test operation

Acenaphtheno is a low-melting organic compound, C{sub 10}H{sub 6}(CH{sub 2}){sub 2}, used as a temperature indicating coating for slugs tested in the Frost Test induction coil. In preparation for this test, slugs are coated by spraying a 12 to 24 per cent by weight solution of acenaphthene in a high vapor pressure solvent on the rotating slug. The solvent evaporate leaving a thin, adherent coating of acenaphthene. This process is completely described in reference 1. To be entirely satisfactory for this use, a solvent must satisfy four requirements. High vapor pressure -- rapid evaporation. Non-flammability. Low toxicity. Carbon tetrachloride, the solvent used at percent, is operationally satisfactory but undersirable because of its toxicity. The purpose of this test is to investigate the suitability of various solvents as substituted for carbon tetrachloride.
Date: June 26, 1951
Creator: Kratzer, W. K.
Object Type: Report
System: The UNT Digital Library
P-10 stack monitoring (open access)

P-10 stack monitoring

On June 14, 1950, an aluminum Kanne Chamber on the 108-B vacuum discharge line was placed in operation. The vacuum pump discharge line chamber has a very poor reputation for two reasons: 1. An apparent hysteresis effect which shows as a high reading after a slug of gas has passed through it, and 2. Failure to return to background current. Cause of the hysteresis effect may be the distribution of tritium in the vacuum pump discharge gas. The rate of gas flow through the Kanne chamber is approximately ten cubic feet per minute. In order to determine steps necessary to eliminate chamber contamination, the existence of contamination must first be definitely established by measuring chamber background with an uncontaminated air filling at intervals during routine use. Monitor chamber currents are now recorded on a multiple point recorder with a cycle time of approximately four minutes, a long wait which is annoying and may mask transient phenomena almost completely. The following steps are recommended to facilitate the necessary stack gas measurements: 1. Provide clean air flushing facilities for both Kanne chambers on the vacuum pump discharge line. 2. Replace existing recorder with continuous recording facilities for each point.
Date: June 26, 1950
Creator: Eisenacher, P. L.
Object Type: Report
System: The UNT Digital Library
ESTIMATION OF ATHEROGENIC INDEX AND ACCUMULATED CORONARY DISEASE IN HUMAN MALES: EVALUATION FROM SERUM GRAVIMETRIC "TOTAL LIPID" OR TOTAL CHOLESTEROL CONCENTRATION (open access)

ESTIMATION OF ATHEROGENIC INDEX AND ACCUMULATED CORONARY DISEASE IN HUMAN MALES: EVALUATION FROM SERUM GRAVIMETRIC "TOTAL LIPID" OR TOTAL CHOLESTEROL CONCENTRATION

None
Date: June 26, 1956
Creator: Nichols, A V; Lindgren, F T & Gofman, J W
Object Type: Report
System: The UNT Digital Library
Quarterly Summary Research Report in Physics for January, February, and March 1954 (open access)

Quarterly Summary Research Report in Physics for January, February, and March 1954

None
Date: June 26, 1954
Creator: unknown
Object Type: Report
System: The UNT Digital Library
ON THE KINETICS OF OXIDATION BY NITRIC ACID (open access)

ON THE KINETICS OF OXIDATION BY NITRIC ACID

A method of predicting the oxidation rates by HNO/sub 3/ in aqueous solutions is indicated by the results of experiments on the ferrous nitroso clock reaction. (auth)
Date: June 26, 1958
Creator: Savolainen, J.E.
Object Type: Report
System: The UNT Digital Library
MODEL STUDIES OF FLOW IN THE THERMAL-SHIELD PASSAGES OF THE PWR REACTOR (open access)

MODEL STUDIES OF FLOW IN THE THERMAL-SHIELD PASSAGES OF THE PWR REACTOR

None
Date: June 26, 1957
Creator: Flanigan, L.J. & Hazard, H.R.
Object Type: Report
System: The UNT Digital Library
ESTIMATION OF NEUTRON SELF ABSORPTION IN RaCO$sub 3$ SAMPLES (open access)

ESTIMATION OF NEUTRON SELF ABSORPTION IN RaCO$sub 3$ SAMPLES

None
Date: June 26, 1950
Creator: Keyes, R.
Object Type: Report
System: The UNT Digital Library
Production of Positive Mesons by Photons on Hydrogen (open access)

Production of Positive Mesons by Photons on Hydrogen

None
Date: June 26, 1950
Creator: Bishop, A. S.; Steinberger, J. & Cook, L. J.
Object Type: Report
System: The UNT Digital Library
A LOW POWER WATER BOILER REACTOR NEUTRON SOURCE (open access)

A LOW POWER WATER BOILER REACTOR NEUTRON SOURCE

None
Date: June 26, 1952
Creator: Biehl, A.T.; Fahrner, T.; Kash, S.W.; Balent, R.; Clark, E.; Howard, D.F. et al.
Object Type: Report
System: The UNT Digital Library
Light Isotopes of Berkelium and Californium (open access)

Light Isotopes of Berkelium and Californium

None
Date: June 26, 1956
Creator: Chetham-Strode, A., Jr.
Object Type: Thesis or Dissertation
System: The UNT Digital Library
ENGINEERING AND ECONOMIC EVALUATION OF COUNTERCURRENT AND FIXED BED ION EXCHANGE PROCESSES. TECHNICAL REPORT NO. 7. Report No. 32 (open access)

ENGINEERING AND ECONOMIC EVALUATION OF COUNTERCURRENT AND FIXED BED ION EXCHANGE PROCESSES. TECHNICAL REPORT NO. 7. Report No. 32

None
Date: June 26, 1953
Creator: Hiester, N.K.; Cohen, R.K. & Phillips, R.C.
Object Type: Report
System: The UNT Digital Library
FATIGUE STUDIES OF INCONEL (open access)

FATIGUE STUDIES OF INCONEL

None
Date: June 26, 1959
Creator: Carlson, R.G.
Object Type: Report
System: The UNT Digital Library
RECOVERY AND PURIFICATION OF URANIUM BY CONTINUOUS ION EXCHANGE AND ELECTROLYSIS (open access)

RECOVERY AND PURIFICATION OF URANIUM BY CONTINUOUS ION EXCHANGE AND ELECTROLYSIS

None
Date: June 26, 1956
Creator: Higgins, I R
Object Type: Report
System: The UNT Digital Library
A NON-DESTRUCTIVE TEST FOR THE IDENTIFICATION OF CADMIUM PLATING (open access)

A NON-DESTRUCTIVE TEST FOR THE IDENTIFICATION OF CADMIUM PLATING

None
Date: June 26, 1953
Creator: Leslie, W.B.
Object Type: Report
System: The UNT Digital Library
Provision for activated silica at 183-B (open access)

Provision for activated silica at 183-B

In some discussions regarding water flow requirements for future pile power increases at the 100-B Area it was agreed that Pile Technology would explore the feasibility of slightly modifying the activated silica facility at 100-C to supply both areas. This letter summarizes the results of the survey and schedules tests which will allow recommendations to be confirmed.
Date: June 26, 1953
Creator: Bupp, L. P.
Object Type: Report
System: The UNT Digital Library
A review of past experiences with H.I. survey problems (open access)

A review of past experiences with H.I. survey problems

This report describes contamination in the 100, 200, and 300 areas at Hanford in 1956.
Date: June 26, 1950
Creator: Thorburn, R. C.
Object Type: Report
System: The UNT Digital Library
Chemical Technology Division, Unit Operations Section Monthly Progress Report for March 1959 (open access)

Chemical Technology Division, Unit Operations Section Monthly Progress Report for March 1959

In a preliminary experiment, the integral diffusivity of 1 M FeCl/sub 3/ solution varied uniformly with the fraction difiused: from 0.3 x 10/sup -6/ cm/ sup 2//sec for 10 per cent diffused to 0.8 x 10/sup -6/ for 30 per cent diffused. A short Fluorox run made with crude UF/sub 4/ in the 4-in. fluidized bed showed that UF/sub 6/ could be produced from the impure feed. Denitration of Th(NO/sub 3/)/sub 4/ solutions on fluidized or mechanically agitated beds of ThO/sub 2/ and gave fine ThO/sub 2/ particles for all conditions tested. The rate of sorption of uranium into 40 micron Dowex 21K resin particles from a 0.0042 M uranyl sulfate solution was studied by measuring the uranium loading on individual beads as a function of time. Chloride concentrations of 28 to 51 ppm were produced in the solvent extraction feeds during five feed adjustment runs made with the Darex Reference flowsheet. Decladding of SS-clad /sub 4/ gave essentially identical results as batch decladding. When a Mark I prototype assembly was sheared into 0.75-in. lengths with a"plane of contact" blade in the 126-ton Manco shear, 22.2 g of metal fines (304L stainless steel) 1680 microns or less in size was …
Date: June 26, 1959
Creator: Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E.
Object Type: Report
System: The UNT Digital Library
Electrolytic Recycle Method for the Treatment of Radioactive Nitric Acid Waste. A Status Report at the Termination of the Project at KAPL (open access)

Electrolytic Recycle Method for the Treatment of Radioactive Nitric Acid Waste. A Status Report at the Termination of the Project at KAPL

A methed is descrihed for the treatment of radioactive neutralized nitric acid waste solutions. The process consists of electrolysis of sodium nitrate solutions and recycle the caustic formed to neutralize incoming nitric acid ate. Removal of a large fraction of the bulk inert substances by this method allows greater reductions in waste volume than conventional treatment by evaporation alone. Process chemistry studies show that a large fraction of the nitrate ion in alkaline solution can be electrolytically reduced to gaseous nitrogen reduction products at reasonable current efficiencies. Process engineering studies have resulted in the development of a prediction equation for the design of electrolysis cells used in the process. Pilot plant studies using cold'' nitric acid waste have demonstrated the feasibility of the electrolytic recycle methed. A preliminary cost estimate was performed which iadicates a cost of from 75 to 95 per initial gallon of waste processed. Basis for this estimate is a conceptual design of a plant capable of handling the highlevel waste produced in reprocessing one ton of uranium metal per day. These costs are considered reasonable in a nuclear power economy, and indications are that ultimate disposal of the concentrated waste in clay may be possible. (auth)
Date: June 26, 1957
Creator: Alter, H. W.; Barney, D. L.; Davidson, J. K.; Schafer, A. C., Jr. & Witt, F. J.
Object Type: Report
System: The UNT Digital Library