ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM. Monthly Progress Report for September 1960

Technical Report · Thu Sep 01 04:00:00 EDT 1960

OSTI ID:4094869

NRTS Operations. Testing of the GCRE with the plate type fuel elements was concluded and this core was removed. The pin type fuel elements were loaded and critical experiments and zero-power tests begun. ML-1 operations are summarized. ML-1. Fabrication of the ML-1 package progressed satisfactorily. The tube bundle assembly was leak tested and control blade mount assemblies were completed. Confirmatory measurements for the shield were made at ORNL. Fuel Element Development. In the IB-2T-1 in-pile test, long-lived fission product activity was noted in the loop gas after increase of outlet gas temperature to 1300 deg F. Materials evaluation results included tensile properties of Hastelloy- X at 1750 deg F and tube burst tests at 2100 to 2300 deg F. Compositions and tensile properties for modifications of Hastelloy-X are given. Advanced Reactor Systems Project. Evaluations of advanced nuclear power plants were made to select a system for an advanced mobile power plant concept. Helium and air were studied as coolants, and closed turbine cycles were compared with opencycle two- fluid systems. Gas Turbine Test Facility. Results of test runs are discussed. (T.R.H.)

• Research Organization: Aerojet-General Nucleonics, San Ramon, Calif.
• NSA Number: NSA-15-010524
• OSTI ID: 4094869
• Report Number(s): IDO-28563
• Country of Publication: United States
• Language: English

Related Subjects

AIR
ALLOYS
ALUMINUM ALLOYS
CHROMIUM ALLOYS
CONTROL ELEMENTS
COOLANT LOOPS
CRITICALITY
FABRICATION
FAILURES
FISSION PRODUCTS
FUEL ELEMENTS
GAS COOLANT
GAS FLOW
GASES
GCRE-1
HASTELLOY
HELIUM
IN PILE LOOPS
LEAKS
MATERIALS TESTING
MEASURED VALUES
ML-1
MOLYBDENUM ALLOYS
NICKEL ALLOYS
ORNL
PLATES
POWER PLANTS
RADIOACTIVITY
REACTOR CORE
REACTOR FUELING
REACTOR TECHNOLOGY
REACTORS
RODS
SHIELDING
TEMPERATURE
TENSILE PROPERTIES
TRANSPORT
TUBES