Some Thermodynamic Properties of Freon-114 (open access)

Some Thermodynamic Properties of Freon-114

Introduction: The thermodynamic properties of Freon-114 presented herein supplement those of Volume I and encompass a range of temperature above the critical to 400 F &176 F.
Date: September 3, 1959
Creator: Van Wie, N. H. & Ebel, Robert A.
System: The UNT Digital Library
Nuclear Superheat Meeting: September 1959 (open access)

Nuclear Superheat Meeting: September 1959

From introduction: The Commission's underlying objective of this program is to conduct sufficient engineering and development work to determine the most feasible and economical methods of producing nuclear super-heated steam from a boiling water reactor.
Date: November 3, 1959
Creator: unknown
System: The UNT Digital Library
Periodic Radiation Survey. Section I. EFPH-4182. First Performance. Core I, Seed 1. Test Results DL-S-231 (T-612394) (open access)

Periodic Radiation Survey. Section I. EFPH-4182. First Performance. Core I, Seed 1. Test Results DL-S-231 (T-612394)

The purpose of the survey was to determine the radiation levels in the 1 D Boiler Chamber during plant operation. The conclusion of this survey is that the radiation level in the 1 D Boiler Compartment with the 1A, 1B, and 1C Main Coolant loops in service at approximately 100 per cent power ranged from .03 MR/HR to 6.0 MR/HR.
Date: November 3, 1959
Creator: Ritz, William C.
System: The UNT Digital Library
Melting Point of Th-U-C Fuel Elements (open access)

Melting Point of Th-U-C Fuel Elements

From the point of view of predicting melting behavior of fuel elements containing fission products after 50 percent burn-up, the fuel can be considered to consist of 2000 moles Th, 150 moles U, 55 moles of rate earth metal, 31 moles of Zr, 25 moles of Mo, 20 moles of Rh-Ru-Tc, and 15 moles of alkaline earth metal. All other fission products are present in too small amounts to have any important effect upon the melting point or will have vaporized. However, the presence of alkali metal vapor should be considered.
Date: August 3, 1959
Creator: Brewer, Leo, 1919-2005
System: The UNT Digital Library
Charging and Discharge of Demineralizer Resins. Section IV. First Performance. Core I, Seed 1. Test Results DL-S-180, T-612085 (open access)

Charging and Discharge of Demineralizer Resins. Section IV. First Performance. Core I, Seed 1. Test Results DL-S-180, T-612085

The purpose of the test was to determine if the 1A Canal Water System Demineralizers can be satisfactorily charged with resin. The 1A Canal Water System Demineralizer was satisfactorily charged with resin and conductivity of the demineralizer effluent was less than 0.1 microbes as specified in the Test Procedure.
Date: December 3, 1959
Creator: Eckenrode, G. E.
System: The UNT Digital Library
The Determination of Decontamination Factors for Radioisotopes Through Lithium Hydroxide Resin. Section I. Second Performance. Core I, Seed 1. Test Results DL-S-277-S, RNI-22 (open access)

The Determination of Decontamination Factors for Radioisotopes Through Lithium Hydroxide Resin. Section I. Second Performance. Core I, Seed 1. Test Results DL-S-277-S, RNI-22

The purpose of the test was to obtain data on the decontamination factors for Cesium-136, Cesium-137, Strontium-92, one hour gross iodine and Iodine-131. This data will be used to determinate efficiency of lithium hydroxide resin for removing radioactive cations and anions. The denomination factors for a particular demineralizer using lithium hydroxide resign were found to vary for different radioisotopes. This variation was from 2.3 for Cesium136 to 77,000 for gross iodine.
Date: December 3, 1959
Creator: Strauos, Roger O.
System: The UNT Digital Library