Standard Practices for Design of MTR and ETR Safety Circuits (open access)

Standard Practices for Design of MTR and ETR Safety Circuits

Report containing notes for designing safety circuits for the Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR).
Date: September 15, 1957
Creator: Jones, L. H.
System: The UNT Digital Library
OMR Control-Safety Rod Component Development Tests (open access)

OMR Control-Safety Rod Component Development Tests

Abstract: A magnetic-jack control-safety rod is under development for the 45.5 thermal megawatt Organic Moderated Reactor. The rod is "unitized," i.e., the poison element, drive, position indicator, and shock absorber are contained in a compact assembly which is inserted in a regular fuel channel opening in the core. Tests to develop components capable of operating under these conditions are described and results are reported.
Date: September 15, 1959
Creator: Howell, J. D.
System: The UNT Digital Library
Coolant Flow and Outlet Temperature: Computer-Monitors for the Hallam Nuclear Power Facility Plant Protective System (open access)

Coolant Flow and Outlet Temperature: Computer-Monitors for the Hallam Nuclear Power Facility Plant Protective System

Abstract: The design and application of two computers for the HNPF protective system is discussed.
Date: September 15, 1961
Creator: Schlein, H.
System: The UNT Digital Library
A Multichannel Digital Recording System (open access)

A Multichannel Digital Recording System

Abstract: This report is a description of a 200 channel digital recording system used to record high temperature strain gage outputs and associated temperatures.
Date: September 15, 1960
Creator: Truitt, R. W.
System: The UNT Digital Library
Carbide Fuels in Fast Reactors (open access)

Carbide Fuels in Fast Reactors

Abstract: Cladding and fuel material processing prospects are reviewed, and fuel system possibilities for near-term (~1 mill/kwh) and long-range (<0.5 mil/kmh) fuel cycles are described.
Date: September 15, 1965
Creator: Wheelock, C. W.
System: The UNT Digital Library
Stress and Elevated Temperature Fatigue Characteristics of Large Bellows (open access)

Stress and Elevated Temperature Fatigue Characteristics of Large Bellows

From abstract: Charts in this report show axial stress distribution over exterior bellows surfaces induced by bellows axial deflection, and by internal pressurization. The influence of root rings on stress distribution is presented graphically.
Date: September 15, 1964
Creator: Winborne, R. A.
System: The UNT Digital Library
Hallam Nuclear Power Facility, Reactor Operations Analysis Program: Semiannual Progress Report Number 3, September 1963-February 1964 (open access)

Hallam Nuclear Power Facility, Reactor Operations Analysis Program: Semiannual Progress Report Number 3, September 1963-February 1964

From introduction: This report provides industry, plant operators, and the scientific community with information covering the results of the performance analysis.
Date: September 15, 1964
Creator: Darley, D. K.
System: The UNT Digital Library