GAS-COOLED REACTOR PROJECT QUARTERLY PROGRESS REPORT FOR PERIOD ENDING DECEMBER 31, 1959
8 < 8 < : D < ; > 7 H 9 @ 7 8 : 9 9 8 9 8 C 8 5 9 8 8 7 9homogeneous representation of the EGCR core yields interpretable results for neutron flux and power distributions that are sufficiently close to the four-group heterogeneous core results to permit valid analyses of the effects of experimental loops on the core. The effects on radial power distribution in the EGCR core of various experimental fuel assemblies in the experimental loops were studied. Preliminary experimental results for a modified EGCR core rod lattice were obtained with the PCTR. The effect of stainless steel cladding on the graphite plugs and sleeves of the Title 1 dummy assemblies was studied. Preliminary calculations were made of the graphite damage that will occur in the EGCR as a result of moderation of fast neutrons. As part of an over-all study of the EGCR experimental loops, it was found that for the "worst" experimental fuel element being studied the circulating fission-product activity to be expected at equllibrium in a 1.5 Mw loop was 7.53 x 10/sup 3/ curies. Calculations were made to determine the effect of reflector thickness and composition on exposure of the pressure vessel to fast neutrons. A study was made of the absorption properties of the U/sup 233/, U/sup 235/, and PU/sup 239/ fission products as a function of the relative burnup of the fue and the degree of flux thermalization. Reacror Design Studies: A modification was made to the Title 1 EGCR fuel assembly which eliminates the need for making the final bcttom weld with the cluster in the graphite sleeve. Fuel handling and coolant flow control provisions were studied to assess the effect of the lifting force of the gas stream on the fuel assemblies. Analysis of preliminary analog studies indicated that the rate of change of temperature of the fuel elements will not cause severe strains in the cladding due to the relative thermal expansion of the cladding and the UO/sub 2/. Studies are being made of deflections and stresses in the fuel element cladding under arbitrary temperature distributions. The first test of a metal-clad graphite body was completed. Studies of the coolant channel flow adjustments required for the EGCR led to a new concept of flow adjustment. The amount and nature of the contamination to be expected in the charge and service machines were studied. An analysis was made of the possibility of core levitation in the EGCR in case of singleended or double-ended failures of the roain exit coolant pipes. Heat Transfer and Fluid Flow: The study of heat transfer in the septafoil geometry was continued using an inlet plenum chamber screen arrangement designed to reduce the rotational component of the flow at the channel entrance. A series of tests using cotton threads to visualize the flow in the channel entrance indicated that a set of three coaxial screens in the inlet plenum region was most effective in reducing the rotational flow observed in earlier studies. Measurement of velocity profiles in the septafoil channel for a gamma = 2 tabe spacing was completed at five additional L/d/sub e/ levels ranging from the channel inlet to the outlet. Metallurgy: The continuous process for conversion to UO/sub 2/ was refined tc the point where satisfactory reproducibility is being obtained. An apparatus for measuring the thermal conductivity of UO/sub 2/ was constructed. A series of compression tests of UO/sub 2/ at high temperature was completed. Equipment was designed and built for observing the mechanical behavior of encapsulated UO/sub 2/ by radiography. An apparatus was built for collecting and measuring the fission gases released from heated specimens of irradiated UO/sub 2/ . Experiments on CO and CO/sub 2/-metal reactions were carried out at pressures as low as 10 mu . An extensive series of tube-burst tests of type 304 stainless steel in various environments is being run. A thermal cycling test of a fuel capsule collapsed around UO/sub 2/ pellets was conducted that consisted of 75 cycles from 1000 to 1600 deg F at a rate of 100 deg F/min. Interim data were obtained on the effect of
- Research Organization:
- Oak Ridge National Lab., Tenn.
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-14-010205
- OSTI ID:
- 4207759
- Report Number(s):
- ORNL-2888
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-60
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ABSORPTION- BURNUP- EGCR- FISSION PRODUCTS- GAS COOLANT- NEUTRON FLUX- PLUTONIUM 239- POWER PLANTS- THERMAL NEUTRONS- URANIUM 233- URANIUM 235
ANNEALING- EGCR- GAS COOLANT- POWER PLANTS- PRESSURE VESSELS- RADIATION EFFECTS- STEELS
BERYLLIUM- BERYLLIUM OXIDES- CARBON DIOXIDE- CARBON MONOXIDE- CHEMICAL REACTIONS- EGCR- GAS COOLANT- HIGH TEMPERATURE- POWER PLANTS
BERYLLIUM- EGCR- FAST NEUTRONS- GAS COOLANT- HIGH TEMPERATURE- POWER PLANTS- RADIATION EFFECTS
CANNING- EGCR- EXPANSION- FUEL ELEMENTS- GAS COOLANT- GRAPHITE- PLANNING- POWER PLANTS- REACTOR CORE- TEMPERATURE- THERMAL STRESSES- URANIUM OXIDES