Title: GAS-COOLED REACTOR PROJECT QUARTERLY PROGRESS REPORT FOR PERIOD ENDING DECEMBER 31, 1960

Abstract

Pebble-Bed Reactor Studies. Design studies were carried out of the pebble-bed reactor which was indicated to be potentially capable of producing low- cost power. A preliminary design was prepared for a 10-Mw experimental reactor with which to obtain sufficient data for the de sign of a full-scale pebble-bed power reactor. The second stady produced a design of a 330-Mw(e) power plant based on a parametric analysis of the design requirements. Reactor Physics. A zons-loading pattern for the EGCR was designed as a compromise between the requirements for power flattering and the desire for high loop power. Reactivity effects associated with operation of the EGCR were studied to obtain data needed for determining the control actions that must be available. Calculations were made of the neutron source required for the EGCR. Studies were made of the flux levels at EGCR shield penetrations and the dose rates around the charge and service machines. calculations of the heat deposition in the EGCR core included the additional heating by gamma rays originating in a loop experiment and the heating effect of fast neutrons. Reactor Design Studies. The thermal behavior of the EGCR fuel asemblies was analyzed in terms of the effect of control programingmore » and mode of operation. Ths ORNL analog computer was used to analyze EGCR fuel temperatures during the following transients: (1) the extremes of the normal conditions; (1) variations caused by loss of gas flow; (3) variations caused by reactivity increases, and (4) variations caused by loss of power. Preliminary designs were prepared for four types of beryllium-clad fuel elements for use in alternate fuel assemblies for the EGCR core. Correlation studies were made of mass- and heat-transfer data applicable to EGCR fuel assemblies. The design of the EGCR control rod was modified, and a full-scale mock-up is being assembled to establish fabricating techniques. A method for deconiuninating EGCR components was developed. A kinetics stady of the oxidation of H/sub 2/, CO, and CH/sub 4/ in a flowing stream of helium in a fixed bed of Girdler G-43 platinum cataalyst was completed. In EGCR hazards evaluations, the possibility of the ignition of graphite if air entered the system because of a rupture was considered. A review of the maximum credible accident postulated for the EGCR was made. An empirical representation of the neutron exposure of the moderator columns in the EGCR was developed for use in evaluating the induced stresses. Fast-neutron exposure leads to bowing of the EGCR graphite columns, and an evaluation of the defection of each column is required as a basis for designing the supports. Instantaneous collapse and creep buckling tests of type 304 stainless-steel cylindrical shells were conducted to obtain data applicable to the experimental tubes in the EGCB. An experimental stress analysis was made of a spherical shell with an attached nozzle in order to check the hypothesis that the total stresses resulting from combined loadings may be obtained by linearly adding the stresses corresponding to each component separately applied, so long as the elastic limit is not exceeded. An analysis was made of means for reducing thermal stress in the region of the junction of the pressure-vessel body and the flange that forms a part of the volute of the compressor for GCR-OHR loop No. 2. Other topics covered include discussions on: Experimental Investigations of Heat- Transfer and Fluid Flow; Materials Development; In-pile Testing of Components and Materials; Out-of-pile Testing of Materials and Components; and Development of Test Loops and Components. (For preceding period see ORNL-3015.)« less

Publication Date:

Wed Mar 01 00:00:00 EST 1961

Research Org.:

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

OSTI Identifier:

4063590

Report Number(s):

ORNL-3049

NSA Number:

NSA-15-013993

DOE Contract Number:  

W-7405-ENG-26

Resource Type:

Technical Report

Resource Relation:

Other Information: Orig. Receipt Date: 31-DEC-61

Country of Publication:

United States

Language:

English

Subject:

REACTOR TECHNOLOGY; BERYLLIUM; BERYLLIUM OXIDES; BRAZING; CARBON DIOXIDE; CARBON MONOXIDE; CARBON STEELS; CHROMIUM ALLOYS; COATING; COOLING; COPPER; CRACKS; CYLINDERS; DENSITY; DISPERSIONS; EGCR; EXTRUSION; FABRICATION; FAILURES; FISSION PRODUCTS; FUEL CANS; FUEL ELEMENTS; GAS COOLANT; GASES; GRAIN SIZE; GRAPHITE; HELIUM; HIGH TEMPERATURE; IN PILE LOOPS; INOR-8; INSPECTION; IRRADIATION; MASS SPECTROMETERS; MATERIALS TESTING; METALLOGRAPHY; MOLYBDENUM ALLOYS; NICKEL ALLOYS; OXIDATION; PARTICLES; PELLETS; PLATES; POWDERS; PRESSURE; PRESSURE VESSELS; REACTORS; SILICON; SILICON CARBIDES; SINTERING; STAINLESS STEELS; TEMPERATURE; THERMAL CONDUCTIVITY; THERMOCOUPLES