Gas cooled fast reactor control rod drive mechanism deceleration unit. Test program

Technical Report · Thu Oct 01 00:00:00 EDT 1981

DOI:https://doi.org/10.2172/5275636· OSTI ID:5275636

Wagner, T H

This report presents the results of the airtesting portion of the proof-of-principle testing of a Control Rod Scram Deceleration Device developed for use in the Gas Cooled Fast Reactor (GCFR). The device utilizes a grooved flywheel to decelerate the translating assembly (T/A). Two cam followers on the translating assembly travel in the flywheel grooves and transfer the energy of the T/A to the flywheel. The grooves in the flywheel are straight for most of the flywheel length. Near the bottom of the T/A stroke the grooves are spiraled in a decreasing slope helix so that the cam followers accelerate the flywheel as they transfer the energy of the falling T/A. To expedite proof-of-principle testing, some of the materials used in the fabrication of certain test article components were not prototypic. With these exceptions the concept appears to be acceptable. The initial test of 300 scrams was completed with only one failure and the failure was that of a non-prototypic cam follower outer sleeve material.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Westinghouse Electric Corp., Madison, PA (United States). Advanced Reactors Div.
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5275636
• Report Number(s): ORNL/Sub-81/92336/1; WARD-GCFR-81-01; ON: DE82014725; TRN: 82-015908
• Resource Relation: Other Information: Portions of document are illegible
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
GCFR REACTOR
SCRAM RODS
BRAKES
PERFORMANCE TESTING
BREEDER REACTORS
CONTROL ELEMENTS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
GAS COOLED REACTORS
GCFR TYPE REACTORS
HELIUM COOLED REACTORS
MACHINE PARTS
REACTOR COMPONENTS
REACTORS
TESTING
220400* - Nuclear Reactor Technology- Control Systems
210500 - Power Reactors
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