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Removal of Xe13' from Molten Fluoride Fuels ............................... 124 Ll TR Horizontal-Beam-Hole Fluor ide-Fuel Loop ............................. 125 Creep and Stress-Corrosion Tests ....................................... 126 Remote Metallography ............................................... 127 Mass Spectrograph i c Ana I y ses ......................................... 127 10 . ANALYTICAL STUDIES OF REACTOR MATERIALS .......................... 129 I Chemistry of Reactor Materials ................................. 129 Determination of uranium metal in fluoride salt mixtures ....................... 129 Determination of trivalent uranium in fluoride fuels .......................... 129 Determination of oxygen in fluoride fuels ................................. 131 Determination of sulfur ............................................. 131 Determination of fluoride in NaF-KF-LiF-base fuels .......................... 132 Petrographic Investigations of Fluoride Fuels ............................... 133 ANP Service Laboratory ............................................. 133 YAND REPROCESSINGOF REACTOR FUEL ....................... 134 oduct Removal ............................................ 134 ns of Fused Salt-Volatility Processes ............................. 137 Aircraft reactor fuels .............................................. 138 Heterogeneous reactor fuels ......................................... 138 PART Ill . SHIELDING RESEARCH 12 . SHIELDING ANALYSIS .............................................. Slant Penetration of Composite Slab Shields by Gamma Rays ..................... 143 143 Emergy Absorption Resulting from Incident Gamma Radiation as a Function of Thickness of Materials with Slab Geometry ................................ A Formulation for Radiation lniury to Include Time Effects ...................... Analysis of Some Preliminary Differential Experiments ......................... 144 145 146 Interpretation of Air and Ground Scattering at the Tower Shielding Facility 147 ............ 13 . LID TANK SHIELDING FACILITY ...................................... 151 Effective Neutron Removal Cross Section of Lithium ........................... 151 GE-ANP Helical Air Duct Experimentation ................................. 153 Reflector-Moderated Reactor and Shield Mockup Tests ......................... 155 14 . BULK SHIELDING FACILITY ......................................... 156 A Search for Short-Half-Life Nuclear Isomers in K39. Rb85. Rb87. and Zr90 ............ 156 15 . TOWER SHIELDING FACILITY ........................................ 158 TSF Experiment with the Mockup of the GE-ANP R-1 Shield Design ................. 158 PART IV . APPENDIX ORGANIZATION CHART OF THE AIRCRAFT NUCLEAR PROPULSION PROJECT 167 U X T ......... 'p:
ANP PRQJECT QUARTERLY PROGRESS REPORT PART 1. REACTOR THEORY, COMPONENT DEVELOPMENT, AND CONSTRUCTION 1. Circulating-Fuel Aircraft Reactor Experiment The Aircraft Reactor Experiment was operated successfully for over 100 Mw/hr. During this time the maximum equilibrium outlet fuel temperature was 158OoF, and the maximum power level was over 2.5 Mw. The temperature coefficient of reactivity 2 min after the introduction of a pertur- bation was -5.5 x although its instantaneous value was considerably higher. As a result, the reactor was extremely stable while operating at power, and there were no control problems. The ciitical mass was 32.5 Ib of U235 and thus was in reasonable agreement. with the calculated value of 30 Ib. Operation of the process systems and their instrumentation was exceptionally trouble-free during the six days of operation*from the time the equipment was sealed in the pits until the sodium and the fuel were dumped. It is believed that most of the fission-product gases evolved from the liquid fuel. In a 25-hr run, it was determined that no more than 1 part in 30 of the xenon poison remained in the fuel. An unexpectedly steep initial slope that was observed in the usual plot of [l - (l/multiplication constant)] was found to be due to the formation of SUMMARY rotary elements functioned satisfactorily. Fuel samples were withdrawn from the ARE during operation below criticality and at very low power. As was anticipated, the chromium content of the fuel increased after each addition of fuel concentrate. Just before the first additions of fuel concentrate were made, the chromium concentration of the carrier material was 100 ppm and the carrier had been circulated for 155 hr. Since the system had been operating isothermally, the chromium content of 100 ppm was considered to represent 0.5 mil of attack on the Inconel. By the time the final sample was taken, after 13 total of 307 hr of operation, the chromium content was 445 ppm, which represents about 5 mils of attack. A plot of the data obtained showed that the chromium content of the fuel had started to level off. Since it was not possible to sample the fuel during full power operation, no information on mass transfer can be obtained until the equipment can be sec- tioned. 2. Reflector-Moderated Reactor The reactor assembly and the installation for the Aircraft Reactor Test (ART), formerly the Circulat ing-Fue I Reactor Experiment (CF RE), have been the subject of analytical layout and detailed design studies. Component development tests are proceeding as scheduled, and specifications have ompleted for o be used as heat in heat exc S. ork has been done on the development of a hydraulic I , ierature level of the power runs temperature to which ARE pumps have been An analysis has been made of the activation of subiected, it was interesting to note that all the Inconel core shells that would come from two
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