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Title: MARITIME GAS-COOLED REACTOR PROGRAM. Quarterly Progress Report for the Period Ending September 30, 1961

Abstract

Included in the MGCR Project are the design, construction, and test operation of a 10-Mw(t) reactor experiment as an intermediate stage to determine the operating characteristics of BeO-moderated gas-cooled systems and to lend greater assurance of success to the subsequent prototype plant. This reactor experiment is known as the Experimental Beryllium Oxide Reactor (EBOR). A number of core design analyses and changes were made. These included: thermal studies to determine allowable temperature conditions for the core element support riser top plate; an investigation to ascertain the need for the bottom head of the thermal shield; and a decision to abandon the concentric duct flow restrictor concept in favor of a pressure vessel design that receives all of the helium flow through the concentric duct. An analysis of the loss-ofcoolant accident for the annular EBOR fuel element was made. Experiments to determine the circumferential variation of the heat transfer coefficient around a fuel rod were initiated. The irradiation of the MGCR-HDR-3 test fuel element in the Hanford DR-1 Gas Loop continued satisfactorily. The ball-nut lead screw environmental test program was completed. A modified 135 Nitralloy screw and tungsten carbide balls were found to constitute the best combination. The assembly of themore » MGCR control rod drive environmental test loop and associated instrumentation was completed. A revised design of the low-pressure turbine-compressor set is 70% complete. Compressor and turbine model testing was continued. Compressor model tests were carried out to determine the effect of stage loading and the effect of stator seal clearance on the performance of the compressor. Emphasis was placed on the incorporation of the DSN multigroup transport code into the EBOR and the critical assembly calculations. In addition, the GAM-1 and GATHER codes for the solution of epithermal and thermal spectra problems, respectively, and for the determination of spectra-averaged cross sections for subsequent diffusion theory calculations, were brought into use. The critical assembly program is continuing. Following the experiments on the lightly loaded simulated water-flooded assembly, the loading was doubled and additional measurements made. Dose rate calculations pertaining to both dry and wet fuel handling were made. The performance of the MGCR-4 fuel irradiation capsule in the MTR continued satisfactorily. The examination of BeO pellets from the MGCR-1 irradiation capsule was also continued. Crushing strengths of up to 88,000 psi were recorded. Extended time creep- rupture testing of Hastelloy-X, in various environments, is being directed toward the determination of the reason for the shorterthan-predicted rupture lives of various specimens. Investigations to determine the aqueous corrosion properties of various metallic materials were started. (auth)« less

Publication Date:
Research Org.:
General Atomic Div. General Dynamics Corp., San Diego, Calif.
OSTI Identifier:
4681608
Report Number(s):
GA-2568
NSA Number:
NSA-17-024676
DOE Contract Number:  
AT(04-3)-187
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-63
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; ACCIDENTS; BERYLLIUM MODERATOR; BERYLLIUM OXIDES; CHROMIUM ALLOYS; COMPRESSORS; CONTROL ELEMENTS; CONTROL SYSTEMS; COOLANT LOOPS; CORROSION; CRACKS; CREEP; CRITICAL ASSEMBLIES; CROSS SECTIONS; DIFFUSION; DR-1; DSN-CODE; EBOR; EPITHERMAL NEUTRONS; FABRICATION; FUEL ELEMENTS; G-CODES; GAS COOLANT; GAS FLOW; GROUP THEORY; HASTELLOY; HDR; HEAT TRANSFER; HELIUM; IN PILE LOOPS; INSTRUMENTS; IRRADIATION; MACHINE PARTS; MATERIALS TESTING; MEASURED VALUES; METALS; MGCR; MOLYBDENUM ALLOYS; MTR; NICKEL ALLOYS; PELLETS; PERFORMANCE; PIPES; PLANNING; PLATES; POWER PLANTS; PRESSURE; PRESSURE VESSELS; PROGRAMMING; RADIATION DOSES; REACTOR CORE; REACTOR FUEL

Citation Formats

. MARITIME GAS-COOLED REACTOR PROGRAM. Quarterly Progress Report for the Period Ending September 30, 1961. United States: N. p., 1963. Web.
. MARITIME GAS-COOLED REACTOR PROGRAM. Quarterly Progress Report for the Period Ending September 30, 1961. United States.
. Thu . "MARITIME GAS-COOLED REACTOR PROGRAM. Quarterly Progress Report for the Period Ending September 30, 1961". United States.
@article{osti_4681608,
title = {MARITIME GAS-COOLED REACTOR PROGRAM. Quarterly Progress Report for the Period Ending September 30, 1961},
author = {},
abstractNote = {Included in the MGCR Project are the design, construction, and test operation of a 10-Mw(t) reactor experiment as an intermediate stage to determine the operating characteristics of BeO-moderated gas-cooled systems and to lend greater assurance of success to the subsequent prototype plant. This reactor experiment is known as the Experimental Beryllium Oxide Reactor (EBOR). A number of core design analyses and changes were made. These included: thermal studies to determine allowable temperature conditions for the core element support riser top plate; an investigation to ascertain the need for the bottom head of the thermal shield; and a decision to abandon the concentric duct flow restrictor concept in favor of a pressure vessel design that receives all of the helium flow through the concentric duct. An analysis of the loss-ofcoolant accident for the annular EBOR fuel element was made. Experiments to determine the circumferential variation of the heat transfer coefficient around a fuel rod were initiated. The irradiation of the MGCR-HDR-3 test fuel element in the Hanford DR-1 Gas Loop continued satisfactorily. The ball-nut lead screw environmental test program was completed. A modified 135 Nitralloy screw and tungsten carbide balls were found to constitute the best combination. The assembly of the MGCR control rod drive environmental test loop and associated instrumentation was completed. A revised design of the low-pressure turbine-compressor set is 70% complete. Compressor and turbine model testing was continued. Compressor model tests were carried out to determine the effect of stage loading and the effect of stator seal clearance on the performance of the compressor. Emphasis was placed on the incorporation of the DSN multigroup transport code into the EBOR and the critical assembly calculations. In addition, the GAM-1 and GATHER codes for the solution of epithermal and thermal spectra problems, respectively, and for the determination of spectra-averaged cross sections for subsequent diffusion theory calculations, were brought into use. The critical assembly program is continuing. Following the experiments on the lightly loaded simulated water-flooded assembly, the loading was doubled and additional measurements made. Dose rate calculations pertaining to both dry and wet fuel handling were made. The performance of the MGCR-4 fuel irradiation capsule in the MTR continued satisfactorily. The examination of BeO pellets from the MGCR-1 irradiation capsule was also continued. Crushing strengths of up to 88,000 psi were recorded. Extended time creep- rupture testing of Hastelloy-X, in various environments, is being directed toward the determination of the reason for the shorterthan-predicted rupture lives of various specimens. Investigations to determine the aqueous corrosion properties of various metallic materials were started. (auth)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1963},
month = {10}
}

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