NUCLEAR SAFETY PROGRAM. Annual Progress Report for Period Ending December 31, 1970

NUCLEAR SAFETY PROGRAM. Annual Progress Report for Period Ending December 31, 1970 [electronic resource]

Reactor Fuel Elements/Failure Of Zircaloy Clad Uranium Oxide (Uo$Sub 2$) Rod Type, Effects Of Coolant Loss On, (E); Reactor Fuel Elements/Temperature Distribution In Liquid Metal Cooled Bundle Arranged, Effects Of Flow Blockage On, (E); Zircaloy/Failure Of Tubes Of, (E); Liquid Metal Fast Breeder Re...

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Bibliographic Details
Online Access: Online Access (via OSTI)
Corporate Author: Oak Ridge National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C. : Oak Ridge, Tenn. : U.S. Atomic Energy Commission ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1971.
Subjects:
Reactor Safety.
Reactors.
Safety Failures.
Fuel Cans.
Fuel Elements.
Loss Of Coolant- - Treat.
Tubes.
Water Cooled Reactors.
Zircaloy.
Coolant Loops.
Failures.
Fuel Element Clusters.
Liquid Flow.
Lmfbr.
Temperature.
Containment.
Methane.
Organic Iodine Compounds.
Performance.
Spray.
Thiosulfates.
Fast Neutrons.
Mechanical Properties.
Nozzles.
Pipes.
Radiation Effects.
Steels.
Carbon.
Combustion.
Fission Products.
Standards.
Data Acquisition Systems.
Information.
Information Retrieval.
Operation.
Hydrogen.
Loss Of Coolant.
Pressurized Water Reactors.
Production.
Radiolysis.
Iodine.
Nuclear Safety Pilot Plant.
Testing.
Coated Fuel Particles.
Corrosion.
Gas Cooled Reactors.
Graphite.
Steam.
N38180* > Power Reactor Development > Safety & Siting.
N38590 > Research & Test Reactors & Critical Assemblies > Test Facilities.
N30130 > Metals, Ceramics, & Other Materials > Metals & Alloys > Properties Evaluations.
N30250 > Metals, Ceramics, & Other Materials > Ceramics & Cermets > Radiation Effects.

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E 1.99:ornl--4647 Available

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