Research and Developement on Fabrication of Pin and Lid Detectors and the Dry Run Interface System, Final Report (open access)

Research and Developement on Fabrication of Pin and Lid Detectors and the Dry Run Interface System, Final Report

Final report on research and development on fabrication of pin and lid detectors and the dry run interface system.
Date: August 31, 1963
Creator: Ziemba, F. P.; Katzenstein, H. S.; Zatzick, M. R. & Bernescut, R.
System: The UNT Digital Library
Fast Neutron Flux Measurements and Analysis in SM-1 and PM-2A Core and Vessel Mockups (open access)

Fast Neutron Flux Measurements and Analysis in SM-1 and PM-2A Core and Vessel Mockups

Abstract: This technical report contains a summary of experimental and analytical work performed on cold clean SM-1 Core II with special components and PM-2A Core I each with thermal shield and vessel mockups. The purpose of this work was to define the neutron intensity and spectra to which the pressure vessels are subjected in order to assess the effect of irradiation on the vessel lifetimes. The radial distributions of the energy dependent neutron flux per unit power in the core and vessel mockups are presented. The uncertainties associated with the measurements are also given. In addition to graphical and tabular presentations of the test results, discussions are provided on the experimental techniques and theory. A review of the analytical models is provided in addition to the calculational results. A special analytical study of the the PM-2A Core I power distribution and absolute power level determination is given. A comparison of the experimental and analytical results is made and conclusions and recommendations presented.
Date: March 31, 1962
Creator: Sontheimer, K. C.; Kemp, S. N.; Lois, L.; Clancy, E. F. & McCool, W. J.
System: The UNT Digital Library
Startup Testing of the PM-2A Nuclear Power Plant (open access)

Startup Testing of the PM-2A Nuclear Power Plant

Abstract: A detailed description of the PM-2A reactor, primary system and instrumentation is presented. A general description of the secondary system and plant arrangement at Camp Century, Greenland is included. The results of the startup physics, shielding, thermal and hydraulics and radiochemistry test are presented. the analysis performed on the shielding and thermal and hydraulic tests is included. The shielding problem at startup and the shielding modification made to the plant are described along with the radiation measurements made in these areas.
Date: March 31, 1962
Creator: McCool, W. J.; Ryan, R. M.; Richards, W. M. S.; Bradley, P. L.; Stephenson, L. D. & Cox, J. F.
System: The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System (open access)

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System

Final design for the 30 megawatt intermediate heat exchanger and steam generator.
Date: January 31, 1962
Creator: Alco Products (Firm)
System: The UNT Digital Library
Health Physics Division Annual Progress Report, July 31, 1961 (open access)

Health Physics Division Annual Progress Report, July 31, 1961

Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory.
Date: October 31, 1961
Creator: Oak Ridge National Laboratory. Health Physics Division.
System: The UNT Digital Library
Fabrication of the PRTR Zircaloy-2 High Pressure Process Tubes (open access)

Fabrication of the PRTR Zircaloy-2 High Pressure Process Tubes

Development of a fabrication process and the manufacture of 95 PRTR process tubes demonstrates that the commercial fabrication of high quality Zircaloy-2 pressure tubing is feasible.
Date: July 31, 1959
Creator: Knecht, R. L.
System: The UNT Digital Library
Pathfinder Atomic Power Plant Technical Progress Report for April 1, 1958 - June 30, 1958 (open access)

Pathfinder Atomic Power Plant Technical Progress Report for April 1, 1958 - June 30, 1958

Pathfinder atomic power plant progress report.
Date: March 31, 1958
Creator: unknown
System: The UNT Digital Library
Gas Cooled Nuclear Reactor Study (open access)

Gas Cooled Nuclear Reactor Study

Study of a gas cooled reactor with design specifications providing for a source of high temperature heat to a stream of helium. This reactor, in turn, is used as a source of heat for the air stream in a gas-turbine power plant.
Date: July 31, 1956
Creator: Thompson, A. S.
System: The UNT Digital Library