skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: GAS-COOLED REACTOR PROJECT QUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, 1959

Abstract

; D = > 6 ; : 6 < 7 8 9 7 9sion theory calculation of the power-density distribution in the EGCR was made in order to reduce the uncertainties in the results of previous calculations. A comparison was made of calculated neutron flux distributions in seven-rod fuel clusters and the preliminary results obtained in the Physical Constants Test Reactor at Harford. Neutron flux ratios for the EGCR lattice cell were calculated for fuel enrichments of 2.0 and 2.6%. Studies were made of the power densities attainable in gas-cooled reactors operated with ceramic material as both fuel and moderator. Extensive studies were conducted to determine how the multiplication factor of a gas-cooled reactor varies with the number of rods in the fuel element cluster, cladding thickness, cladding material, inter-rod spacing, lattice pitch, solid and cored rods, fuel enrichment, and fuel-tomoderator ratio. Reactor Design Studiesi A theoretical study is being conducted of the deflections and stresses in fuel element cladding based on arbitrary temperature distributions. Tests were run to determine the load-carrying ability of the threaded-pin-type graphite column joints proposed for the EGCR. A test program was initiated for studying the behavior of metal-clad graphite bodies. An analytical model formore » investigating temperature structure and thermal stability of a seven rod fuel element cluster was developed. Calculations were made of the nataral frequencies aud an amplitude of vibrations in the EGCR fuel element clusters. A parametric study was completed from which the diameter of the coolant channel, pressure drop across the core, and pumping power can be evaluated for a helium-cooled reactor fueled with UO/sub 2/ clad with stainless steel. A detailed analysis was made of the He purification system needed for limiting graphite bunnup and carbon mass transfer in the EGCR. In a design study of advanced steam generators, data were obtained wtth which to evaluate the effects of fin height and tube diameter on the pressure vessel. Experimental Investigations of Heat Transfer and Fluid Flows The study of heat transfer in the septafoil geometry was reoriented toward establishing the criteria for the thermomechanical stability of the tubes in a seventube bundle when a nonuniform circumferential temperature distribution exists. To determine whether the crossflow indicated by the heat-transfer measurements was the result of channel inlet conditions, one of the peripheral tubes in the heat-transfer apparatus was replaced by a naphthalene-coated rod. A preliminary measurement of the velocity distribution for downstream in a septafoil channel having a gamma = 2 tube spacing was completed. Metallurgy Compression testing of high-density UC/sub 2/ has shown it to withstand loads of 5000 psi at 1500 deg C with only moderate deformation. Data were obtained from tube-burst tests of fuel capsule tubing at 1800 deg F which show that results previously reported must be corrected. A series of modified tube-burst tests was conducted to complete the evaluation of the end-closure joints. Results from strain cycling of capsule tubing indicate that temperature has no influence on the number of cycles to failure. Brazing studies on simulated spacers for the mid-plane of the fuel elements were initiated, and the optimum diametral gap between spacer and tube wall was determined. The reactions of stainless steel with low levels of contaminants tn He and Ar are being studied. Welding tests were conducted on cast fuel element hanger material. Development work is being performed on reference standard defects for eddy-current inspection of tubing. Diffusion bonding and brazing of Be were stadied. Evaluations of extruded tubing from England revealed considerable dimensional variation A survey of available data on the reactions of Be with gases was completed. In-pile Testing of Components and Materials; Initial operation of the GETR helium loop revealed the need for several design changes. A new capsule was designed« less

Publication Date:
Research Org.:
Oak Ridge National Lab., Tenn.
OSTI Identifier:
4218973
Report Number(s):
ORNL-2835
NSA Number:
NSA-14-004129
DOE Contract Number:  
W-7405-ENG-26
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-60
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; ARGON- BERYLLIUM- BONDING- BRAZING- CHEMICAL REACTIONS- EGCR- EXTRUSION- FAILURES- FUEL ELEMENTS- GAS COOLANT- HELIUM- HIGH TEMPERATURE- JOINTS- METALLURGY- POWER PLANTS- PRESSURE- REACTORS- STAINLESS STEELS- TESTING- TUBES- URANIUM OXIDES- WELDING; BURNUP- CLEANING- EGCR- FINS- FUEL CANS- FUEL ELEMENTS- GAS COOLANT- GRAPHITE- HELIUM- JOINTS- PLANNING- POWER PLANTS- PRESSURE- PRESSURE VESSELS- REACTOR CORE- REACTORS- STAINLESS STEELS- STEAM- TEMPERATURE- TESTING- THERMAL STRESSES- URANIUM OXIDES- VARIATIONS- VIBRATIONS; CERAMICS- DIFFUSION- DISTRIBUTION- EGCR- ENRICHMENT- FUEL CANS- FUEL ELEME

Citation Formats

. GAS-COOLED REACTOR PROJECT QUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, 1959. United States: N. p., 1959. Web. doi:10.2172/4218973.
. GAS-COOLED REACTOR PROJECT QUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, 1959. United States. https://doi.org/10.2172/4218973
. Tue . "GAS-COOLED REACTOR PROJECT QUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, 1959". United States. https://doi.org/10.2172/4218973. https://www.osti.gov/servlets/purl/4218973.
@article{osti_4218973,
title = {GAS-COOLED REACTOR PROJECT QUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, 1959},
author = {},
abstractNote = {; D = > 6 ; : 6 < 7 8 9 7 9sion theory calculation of the power-density distribution in the EGCR was made in order to reduce the uncertainties in the results of previous calculations. A comparison was made of calculated neutron flux distributions in seven-rod fuel clusters and the preliminary results obtained in the Physical Constants Test Reactor at Harford. Neutron flux ratios for the EGCR lattice cell were calculated for fuel enrichments of 2.0 and 2.6%. Studies were made of the power densities attainable in gas-cooled reactors operated with ceramic material as both fuel and moderator. Extensive studies were conducted to determine how the multiplication factor of a gas-cooled reactor varies with the number of rods in the fuel element cluster, cladding thickness, cladding material, inter-rod spacing, lattice pitch, solid and cored rods, fuel enrichment, and fuel-tomoderator ratio. Reactor Design Studiesi A theoretical study is being conducted of the deflections and stresses in fuel element cladding based on arbitrary temperature distributions. Tests were run to determine the load-carrying ability of the threaded-pin-type graphite column joints proposed for the EGCR. A test program was initiated for studying the behavior of metal-clad graphite bodies. An analytical model for investigating temperature structure and thermal stability of a seven rod fuel element cluster was developed. Calculations were made of the nataral frequencies aud an amplitude of vibrations in the EGCR fuel element clusters. A parametric study was completed from which the diameter of the coolant channel, pressure drop across the core, and pumping power can be evaluated for a helium-cooled reactor fueled with UO/sub 2/ clad with stainless steel. A detailed analysis was made of the He purification system needed for limiting graphite bunnup and carbon mass transfer in the EGCR. In a design study of advanced steam generators, data were obtained wtth which to evaluate the effects of fin height and tube diameter on the pressure vessel. Experimental Investigations of Heat Transfer and Fluid Flows The study of heat transfer in the septafoil geometry was reoriented toward establishing the criteria for the thermomechanical stability of the tubes in a seventube bundle when a nonuniform circumferential temperature distribution exists. To determine whether the crossflow indicated by the heat-transfer measurements was the result of channel inlet conditions, one of the peripheral tubes in the heat-transfer apparatus was replaced by a naphthalene-coated rod. A preliminary measurement of the velocity distribution for downstream in a septafoil channel having a gamma = 2 tube spacing was completed. Metallurgy Compression testing of high-density UC/sub 2/ has shown it to withstand loads of 5000 psi at 1500 deg C with only moderate deformation. Data were obtained from tube-burst tests of fuel capsule tubing at 1800 deg F which show that results previously reported must be corrected. A series of modified tube-burst tests was conducted to complete the evaluation of the end-closure joints. Results from strain cycling of capsule tubing indicate that temperature has no influence on the number of cycles to failure. Brazing studies on simulated spacers for the mid-plane of the fuel elements were initiated, and the optimum diametral gap between spacer and tube wall was determined. The reactions of stainless steel with low levels of contaminants tn He and Ar are being studied. Welding tests were conducted on cast fuel element hanger material. Development work is being performed on reference standard defects for eddy-current inspection of tubing. Diffusion bonding and brazing of Be were stadied. Evaluations of extruded tubing from England revealed considerable dimensional variation A survey of available data on the reactions of Be with gases was completed. In-pile Testing of Components and Materials; Initial operation of the GETR helium loop revealed the need for several design changes. A new capsule was designed},
doi = {10.2172/4218973},
url = {https://www.osti.gov/biblio/4218973}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {12}
}