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04 nuclear safety: pressure piping crack monitoring detection of metal overstress by acoustic emission. Progress report, July-September 1966

Description: The three main areas of effort have been: (1) definition of the general acoustic response pattern related to the gross aspects of forming and extending a crack in various materials, (2) development of a monitor system prototype concept exclusive of transducers and (3) development of a suitable, high temperature transducer. Tests using double cantilever beam (DCB) specimens of various materials to establish conditions of crack formation and growth have indicated that material ductility is a majo… more
Date: October 28, 1966
Creator: Hutton, P H
Item Type: Refine your search to only Report
open access

710 Mockup No. 1 critical experiment. Summary data report

Description: Declassified 21 Sep 1973. A summary of the experiments associated with the three uniformly loaded core configurations related to the 710 Mockup 1 Critical Experiment Reactor is presented. These configurations mocked up specific features of the then current 710 reactor experiment design. The experimental areas included initial loading, neutron lifetime, fission ratios, reflector control methods, reactivity coefficients and power distribution measurements. A major portion of the effort was applie… more
Date: October 21, 1966
Creator: Sims, F. L.; Kunze, J. F.; Pincock, G. D. & Chase, P. L.
Item Type: Refine your search to only Report
open access

Annual Report to Congress 1966

Description: Progress in the Plowshare program during 1966 was characterized by the upsurge of interest by industry in the contained applications of nuclear explosions for gas and oil stimulation, storage and disposal, recovery of oil from oil shales, and mining. Advances in the excavation area were limited to improved code calculations as no field experiments were conducted.
Date: October 31, 1966
Item Type: Refine your search to only Report
open access

Atlas of Irradiated Fuel Structures

Description: Compilation of photographs, photomicrograph mosaics of fuel element cross-sections, and autoradiographs of irradiated fuels. These images were colleted to understand in-reactor fuel kinetics and illustrate structural changes that occur during irradiation of ceramic fuel elements.
Date: October 1966
Creator: Horn, G. R.
Item Type: Refine your search to only Book
open access

Cryogenic Test Plan

Description: The plan defines he XE Cryogenic Test Programs for the Upper Trust Structure components, UTS Test Segment and the UTSM/Shield?TSA Assembly. It includes a description of the test items, the test objectives, tests to be performed, assembly and installation, and the post-test operations.
Date: October 1, 1966
Item Type: Refine your search to only Report
open access

Design criteria for phase II dummy hydraulic core for containment systems experiment reactor simulator

Description: The design of a Phase II dummy hydraulic core for the CSE reactor simulator is described. The core will be a scale model having features typical of PWR or BWR reactor cores, and will include control rods and associated support mechanisms, fuel elements, a thermal shield, top and bottom core guide and support plates, and flow baffles. The core and simulator vessel will be instrumented to provide measurement of temperature, static and differential pressures, forces on core components, and rarefac… more
Date: October 3, 1966
Creator: Henager, C. H.
Item Type: Refine your search to only Report
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