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Title: MARITIME GAS-COOLED REACTOR PROGRAM. QUARTERLY PROGRESS REPORT FOR THE PERIOD ENDING SEPTEMBER 30, 1959

Abstract

Reactor Development. Studies were continued on a prototype design which incorporates an outlet gas temperature of 1,300 tained F and a graphite-moderated, graphitereflected system. Further studies and evaluations showed that in both over-all efficiency and economy, a BeOmoderated system is superior to a graphite core. Studies are also being made of the problems of fuel loading and handling equipment and reactor controls and instrumentation. The air- flow test stand for simulating the operation of a fuel element was used to test several 19-rod bundles, and the hot channel factor for various conditions was calculated. Other work included measuring the thermal conductivity of various insulating materials in a helium atmosphere, investigating the feasibility of using water, in place of inlet gas, as an emengency coolant for a graphite system, and testing a high heat flux heater for the future thermal mark-up of the fuel element. A series of thermalcycling tests was run to determine the most reliable type of fuel pellet and cladding assembly. Fluid Systems and Plant Arrangement. Revision and condensation of the system transient equations were continued. Analysis of the heat-transfer test data is continuing. A further study of the tolerable impurity level for a He-cooled graphitemcderated core wasmore » made. Rotating Machinery. The analysis of the turbine flow path was completed. A secondseries program involving the testing and evaluation of seals, bearings, and systems which are simplified and improved versions of those tested in the first-series tests was initiated. Tests of six lubricating oils were completed during the quarter. Reactor Physics. Thetransient temperature behavior of the fuel in the MGCR critical facility was investigated. A survey of cores was undertaken in order to compate BeO and graphite as moderators and to perform a preliminary optimization of the BeO reactor. ternary system is nearing completion. Problems concerning the staining of the matrix in Al/sub 2/O/sub 3/--UO/sub 2/ fuel bodies during sintering and the effect of other additives on the sintering behavior of high-purity alumina were investigated. Work on metal-graphite reactions is reported. A number of creep tests were run on Inconel. (For preceding pericd see GA-1099.) (W.L.H.)« less

Publication Date:
Research Org.:
General Atomic Div., General Dynamics Corp., San Diego, Calif.; General Dynamics Corp. Electric Boat Div., Groton, Conn.
OSTI Identifier:
4181370
Report Number(s):
GA-1183
NSA Number:
NSA-14-021117
DOE Contract Number:  
AT(04-3)-187
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-60
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; EQUATIONS; FLUID FLOW; GAS COOLANT; GRAPHITE MODERATOR; HEAT TRANSFER; HELIUM; IMPURITIES; TESTING; TRANSIENTS

Citation Formats

. MARITIME GAS-COOLED REACTOR PROGRAM. QUARTERLY PROGRESS REPORT FOR THE PERIOD ENDING SEPTEMBER 30, 1959. United States: N. p., 1960. Web.
. MARITIME GAS-COOLED REACTOR PROGRAM. QUARTERLY PROGRESS REPORT FOR THE PERIOD ENDING SEPTEMBER 30, 1959. United States.
. Mon . "MARITIME GAS-COOLED REACTOR PROGRAM. QUARTERLY PROGRESS REPORT FOR THE PERIOD ENDING SEPTEMBER 30, 1959". United States.
@article{osti_4181370,
title = {MARITIME GAS-COOLED REACTOR PROGRAM. QUARTERLY PROGRESS REPORT FOR THE PERIOD ENDING SEPTEMBER 30, 1959},
author = {},
abstractNote = {Reactor Development. Studies were continued on a prototype design which incorporates an outlet gas temperature of 1,300 tained F and a graphite-moderated, graphitereflected system. Further studies and evaluations showed that in both over-all efficiency and economy, a BeOmoderated system is superior to a graphite core. Studies are also being made of the problems of fuel loading and handling equipment and reactor controls and instrumentation. The air- flow test stand for simulating the operation of a fuel element was used to test several 19-rod bundles, and the hot channel factor for various conditions was calculated. Other work included measuring the thermal conductivity of various insulating materials in a helium atmosphere, investigating the feasibility of using water, in place of inlet gas, as an emengency coolant for a graphite system, and testing a high heat flux heater for the future thermal mark-up of the fuel element. A series of thermalcycling tests was run to determine the most reliable type of fuel pellet and cladding assembly. Fluid Systems and Plant Arrangement. Revision and condensation of the system transient equations were continued. Analysis of the heat-transfer test data is continuing. A further study of the tolerable impurity level for a He-cooled graphitemcderated core was made. Rotating Machinery. The analysis of the turbine flow path was completed. A secondseries program involving the testing and evaluation of seals, bearings, and systems which are simplified and improved versions of those tested in the first-series tests was initiated. Tests of six lubricating oils were completed during the quarter. Reactor Physics. Thetransient temperature behavior of the fuel in the MGCR critical facility was investigated. A survey of cores was undertaken in order to compate BeO and graphite as moderators and to perform a preliminary optimization of the BeO reactor. ternary system is nearing completion. Problems concerning the staining of the matrix in Al/sub 2/O/sub 3/--UO/sub 2/ fuel bodies during sintering and the effect of other additives on the sintering behavior of high-purity alumina were investigated. Work on metal-graphite reactions is reported. A number of creep tests were run on Inconel. (For preceding pericd see GA-1099.) (W.L.H.)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1960},
month = {10}
}

Technical Report:
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