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Flow Decay After an Electrical Power Outage in the PRTR
Previously, W. S. Figg and T. W. Ambrose (HW-51767 Rev) have investigated the problem of flow decay following electrical power loss to the PRTR primary coolant pumps. However, since the time of their study many reactor piping changes have been made in the design; therefore, it has become advisable to re-examine the problem incorporating these changes.
Date:
February 6, 1959
Creator:
Muraoka, J.
System:
The UNT Digital Library
PRTR Hazard Analysis For Various Mechanical Failures
The hazards associated with several possible mechanical failures were analyzed for the PRTR. The consequences of these failures were evaluated for inclusion in the Final Hazards Summary Report.
Date:
July 6, 1959
Creator:
Muraoka, J.
System:
The UNT Digital Library
Specification for Requisition G-3855923Xircalogy-4 Jacket Tubing
This specification is specifically designed for the procurement of Zircaloy tubing to be used in the of swaged, UO fuel elements, an, and the Pu fuel elements for the Plutonium Recycle Test Reactor. Requisition G-385923 contains the following information pertinent to this specification: 1. Dimensions and dimensional tolerance. 2. Source of zirconium sponge and conditions for us of Zircaloy scrap. 3. Inspection requirements. 4. Shipping instructions.
Date:
November 6, 1959
Creator:
Oakes, H. P.
System:
The UNT Digital Library
Confinement System Instrumentation
Instrumentation shall be provided as shown on the attached drawing, SK-1-26835 for Confinement System Control. The Primary objective of the confinement system shall be to provide maximum possible confinement of contamination, consistent with building limitations, in the event of any contamination, consistent with building limitations, in the event of any credible reactor accident resulting from equipment failure or reactor mis operation.
Date:
November 6, 1959
Creator:
Richards, W. A.
System:
The UNT Digital Library