Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1961 - March 1, 1962 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1961 - March 1, 1962

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: April 1, 1962
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
System: The UNT Digital Library
An Evaluation of Four Processes for Recovering Uranium from Zirconium Fuels at the Idaho Chemical Processing Plant (open access)

An Evaluation of Four Processes for Recovering Uranium from Zirconium Fuels at the Idaho Chemical Processing Plant

Report evaluating the technical and economic feasibility of four zirconium fuel processes: the present STR process, the modified Zirflex process, the barium fluozirconate process, and the sodium formate process.
Date: April 27, 1962
Creator: Burn, P.
System: The UNT Digital Library
Unitized Microfilm System for Engineering Drawings of Idaho Operations Office, USAEC and Its Contractors (open access)

Unitized Microfilm System for Engineering Drawings of Idaho Operations Office, USAEC and Its Contractors

Report that describes an engineering drawing microfilm system that was developed for the United States Atomic Energy Commission's Idaho Operations Office and its contractors at the National Reactor Testing Station.
Date: April 16, 1962
Creator: Masterson, Richard G.
System: The UNT Digital Library
Gas-Cooled Reactor Project Quarterly Progress Report: December 1961 (open access)

Gas-Cooled Reactor Project Quarterly Progress Report: December 1961

Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project.
Date: April 6, 1962
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 1. Cost Analysis and Future Development (open access)

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 1. Cost Analysis and Future Development

First part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. I-ii).
Date: April 1962
Creator: Combustion Engineering, inc. Nuclear Division.
System: The UNT Digital Library
ABWR Design and Development Quarterly Progress Report, January 1 Through March 31, 1962 (open access)

ABWR Design and Development Quarterly Progress Report, January 1 Through March 31, 1962

Quarterly design and development progress report on the activities of the Army Boiling Water Reactor (ABWR) Program.
Date: April 15, 1962
Creator: Combustion Engineering, inc. Nuclear Division.
System: The UNT Digital Library
Corrosion of Zircaloy in Crevices under Nucleate Boiling Conditions (open access)

Corrosion of Zircaloy in Crevices under Nucleate Boiling Conditions

Abstract: The MSAR corrosion test loop was used to study the effect of VKE-shaped crevices on the corrosion resistance of Zircaloy under boiling heat-transfer condtions in both ammoniated and lithiated water at pH 10.5.
Date: April 1962
Creator: Anderson, W. Kermit & McGoff, M. J.
System: The UNT Digital Library
Supplement to Reactor Containment Design Study (open access)

Supplement to Reactor Containment Design Study

Summary: Report SL-1868 is a technical and economic feasibility study of four containment methods, i.e., standard containment, pressure relief, pressure supression and low pressure containment, for 44 MWe direct cycle and 180 and 300 MWe dual cycle boiling water reactor plants.
Date: April 23, 1962
Creator: Johnson, R. A. & Nelson, I.
System: The UNT Digital Library
The FAIM Code: a Multigroup, One-Dimensional Diffusion Equation Code (open access)

The FAIM Code: a Multigroup, One-Dimensional Diffusion Equation Code

Abstract: FAIM is a general multigroup, one-dimensional diffusion equation code programmed in FORTRAN language for the IBM 7090 computer.
Date: April 15, 1962
Creator: Baller, D. C.
System: The UNT Digital Library
Accurate Nuclear Fuel Burnup Analyses; First Quarterly Report, (December 1961 - February 1962) (open access)

Accurate Nuclear Fuel Burnup Analyses; First Quarterly Report, (December 1961 - February 1962)

The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date: April 1, 1962
Creator: Rider, B. F.
System: The UNT Digital Library