CVTR IN-PILE LOOP TEST. Terminal Report

Technical Report · Sat Sep 01 04:00:00 EDT 1962

OSTI ID:4718513

Duncan, R N

The successful operation of an engineering proof test of a scaled-down prototype CVTR fuel element and pressure tube verified the reference design concept, fabrication methods, and choice of materials for the CVTR plant. The in- pile loop thimble was tested in the reflector region of the Westinghouse Test Reactor under conditions similar to those expected in the CVTR plant. No failures or major problem areas attributable to the design of the CVTR core were encountered. The use of gasketed transition joints between Zircaloy and stainless steel pressure tube components for long periods of time under adverse conditions was shown to be practical. Gas leakage through the gasketed transition joints was observed during the in-pile loop test operation requiring more frequent additions of hydrogen (deuterium in the CVTR) to maintain the desired overpressure in the cooling water. No evidence of accelerated corrosion, fretting, or mechanical failure of high quality Zircaloy was found. (auth)

• Research Organization: Westinghouse Electric Corp. Atomic Power Div., Pittsburgh
• NSA Number: NSA-17-026847
• OSTI ID: 4718513
• Report Number(s): CVNA-158
• Country of Publication: United States
• Language: English

Related Subjects

CORROSION
CVTR
DEUTERIUM
FABRICATION
FAILURES
FUEL ELEMENTS
GASES
HYDROGEN
IN PILE LOOPS
JOINTS
LEAKS
MECHANICAL PROPERTIES
PLANNING
PRESSURE VESSELS
REACTOR CORE
REACTOR TECHNOLOGY
REACTORS
REFLECTORS
STAINLESS STEELS
TESTING
TUBES
WATER COOLANT
ZIRCALOY