References for Section 1 8 2. GAMMA SCANS OF PRIMARY LOOP PIPING 8 2.1 Primary Circuit Description and Scanning Locations 8 2.2 Detection Equipment and Calibration Methods 11 2.3 Data Summary of Primary Loop Gamma Scans l6 2.k Discussion of Primary Loop Gamma Scan Data 23 References for Section 2 26 3. PRIMARY COOLANT SAMPLERS FOR GASEOUS RADIONUCLIDES AND PARTICULATES 26 3.1 Description of Experiment 26 3.2 Tabulated Results ^0 3.2.1 Radionuclide inventories on sample components .... ^-0 3.2.2 Dust collected on impactor stages and filters .... ^-0 3-3 Axial Distributions in Sampler Diffusion Tubes and Nozzles 65 3 .3 • 1 Diffusion tubes 65 3.3*2 Axial distributions on sampler nozzles 67 3.h Discussion of Diffusion Tube Results 77 3A.I Theoretical behavior of diffusion tubes 77 3.U.2 Effect of the nozzle on coolant sampler performance 79 3.^-.3 Axial distribution of nuclides on the sampler diffusion tubes 8l References for Section 3 88 k. FISSION GAS CONCENTRATIONS IN THE PRIMARY COOLANT AND CORE PURGE GAS 89 k.l General Description of Fission Gas Experiment 89 k. 2 Experimental Methods 91 k. 2.1 December 1970 experiment 91 ^-.2.2 February 1973 measurements 9h k.2.3 September 1973 measurements 98 k.3 Release-to-Birth Rate Ratios of Fission Gases 108 k.h Discussion of Fission Gas Determination 109 References for Section k 113 5-ANALYSES OF DUST COLLECTED IN THE CYCLONE SEPARATORS AND FROM THE EXTERIOR SURFACE OF THE FUEL ELEMENTS 113 5.1 Dust Collection Method 113 5.2 Summary of Cyclone Separator Dust Data 117 5.3 Density Separation of Sample D3 by Zonal Centrifugation . 12^ 5.3.1 Top fraction 128 5.3.2 Second fraction 129 5.3.3 Third fraction 129 5.3 .k Fourth fraction 129 5.h Scanning Electron Microscope (SEM) Photographs of Particles in Samples D3 and D4 Size Fractions 130 5.5 Further Particle Size Distribution Data Emphasizing 0.1 to 10 urn Size Range ll+8 5.6 Characterization of "Soot" Collected from Exterior Surface of Fuel Elements 153 5.7 Dust Concentration and Production Rate in the Primary System 159 References for Section 5 l6l APPENDIX A: DOCUMENTATION OF GAMMA SPECTROSCOPY METHODS 163 Al. Reference Nuclear Data Source 163 A2. Measurement of Photopeak Count Rates and Energies 163 A2.1 Peak finding and single peak measurement 163 A2.2 Analysis of multiplet peak regions l66 A3. Counting Efficiencies 168 A3.1 Usage of counting efficiencies l68 A3-2 Experimental determination of counting efficiencies 169 A3.2.1 Hot-valve cooling line 170 A3 .2.2 Primary circuit piping 170 A3.2.3 Gaseous diffusion tubes 172 A3.2 .k Purge gas vials and flow cells 172 kk. Formula Used to Compute Activities and Fission Gas Concentrations 173 References for Appendix A 1

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This report was prepared at an account of work sponsored by the Unitad Stares Government. Neither the Unitad States nor aha United States Atomic Enanjy Cornmiaeion. nor any of tfteir amployaai. nor any of dwir contractors. fubcontractors, or their ampioyaas. makes any warranty, e«prees or implied, or aaiumai any legal haMify or tesponeifcility for the accuracy, completeness or uaafutnass of any information, apparatus, product or process discioead. or represents thet its use would not infrmaa privately owned n(hts. CRNL-4926 UC-77 i,t* Cooled Reactor Technology Contract No. V-7405-eng-2b CHEMICAL TECHNOLOGY DIVISION Chemical Development Section A Ail ANALYSIS OF CHEMICAL FAILURE OF COATED 1*0, A»D OIHER OXIDE FUE1S IN THE HIGH-TOffERAlUKt GAS-COGLED RSACTOR T. B. Lln4emer H. J. d* ffsrdimll

2.4 Sources of Error in Experimental Measurements and Calculations 19 2.4.1 Possible Errors in Measurements 19 2.4.2 Possible Errors Involved in the Use of the Constant-Potential Equations 3. CHARACTERIZATION AND HISTORY OF MATERIALS USED 3.1 Characterization Procedures for Pyrocarbon Coatings. ... 3.2 Properties of Coated Particles Used in the Annealing Experiments 3.3 Bonded Fuel Pellets 3.4 Irradiation Data 3.5 Ceramographic Examination of Coated Particles 3.5.1 Group A Coated Particles 3.5.2 Groups C and F Coated Particles 4. EXPERIMENTAL RESULTS 4.1 Results of Early Experiments 4.2 Experimental Results on the Release of Cesium 4.2.1 Typical Graphs of Cesium Release vs Annealing Time 4.2.2 Measured and Calculated Parameters Relating to Cesium Release 4.3 Experimental Results on the Release of Barium, Strontium, and Cerium IV Page 4.3.1 Graphs of Fission Product Release vs Annealing Time 4.3.2 Coated-Particle Dimensions and Other Data DISCUSSION OF RESULTS 50 5.1 The Apparent Cesium Diffusion Coefficients 5.2 Evidence of a Concentration Limit in the Outer Coating. . 5.3 Evidence of a Trapped Fraction of Cesium 5.4 Abrupt Changes in Source Potential 5.5 Distribution of Fission Products in an Annealed Fuel Pellet 5.6 Barium, Strontium, and Cerium Results RECOMJ"[ENDATIONS 6.1 The Diffusion Coefficient 6.2 Limit of Cesium Concentration in the Coating 6.3 The Partition Coefficient 6.4 Trapped Fraction of Cesium 6.

This report describes the postlrradiation examinations of driver fuel element EO6-OI, which had been irradiated an equivalent of 38^ full-power days in Peach Bottom, Unit 1. The fuel element is described in detail and its temperature and irradiation service history briefly outlined. Results presented include: (l) visual observations; (2) critical dimensions of fuel compacts, sleeve, and spine: (3) axial distributions of gamma-emitting nuclides plus H and Sr; {k) radial distributions of these nuclides in the sleeve and spine at three axial locations in the fueled regions and three locations in the upper reflector; (5) metallographic examination of samples of fuel compact material; and (6) burnup determinations via radiochemical analyses at two compact locations.