BETTIS TECHNICAL REVIEW. REACTOR CHEMISTRY AND PLANT MATERIALS
An extended series of dynamic tests of clad-anddefected pre-irradtated specimens of U- Mo alloy and UO/sub 2/ fuel materials was carried out in out-of- pile loops. The series of thsts contrasthd the major differences in the bahavior of alloy and oxide fuel maturial during failure of fuel elementh. Corrosion tests of bare, coldpressed, and sintered UO/sub 2/ pellets have thdicathd that high oxygen concentrattons th the coolant at operattng thmperatures will result in oxidatton of exposed UO/sub 2/ at neutral, high, or low pH conditions. Out-of- pile thsts were run to determine the extent of deterioratton and contamination resulting from the offect of oxygenated water (600 deg F) on clad, dofected PWR fuel elementh. Van de Graaff studies were undertaken tn determine what variables are involved in the phenomenon of preferential depositton of crud on fuel element surfaces. From experiments it is concluded that neither surface finish nor galvanic coupling has any appreciable effect on corrosion resistaace of carbon sthel under reactor operating conditions. Corrosion of shield tank materials (carbon steel, copper, and lead) was investigated in an inhibiting solution of lithium chromate. Results indicate that the solution is effective for at least six months. Montmorillonite clay was considered as a possible means of decontaminating waste liquors from PWR. Bench-scale experiments were run with simulated wasts liquors which were treated in a small clay column. The clay will not remove, by exchange, all types of products and its use appears to be limited. In the event of a primary system lenk in PWR, as efficient means for removing radioiodine from the plant container air is required. Chemical Warfare Service and filter-type air monitors were found to be approximately 90% effective in this application. An analytical train was designed to measure properties of the primary coolant water th PWR. The design and testing of the prototype is described. Testing proved the assembly to be satisfactory. Test data have been accumulated on a new instrumental method for measuring the concentration of hydrogen gas dissolved in wathr. The method is based on the fact that the electrical resistance of palladium metal is changed when in contact with water containing dissolved hydrogen. An investigation was made tn determine whether nitric acid cleanisg of sensitized type 304 stainless stnel results in intergranular attack. The magnetic induction behavior of AISI types 410, 405, and 430 and 17-4 PH and AM 255 stainless steels is several heat-treated conditions was studied. A standard cutting machine, designed to open seal weld closures of control rod drive mechanisms and fuel ports, has been designed to meet rigid space requirements and still retain adaptability features. This cutter is composed of three standard components: the power package, the drive head, and the torque tube. The Central Technical Activities autoclave facility is responsible for much of the actual corrosion, wear, and friction testing done on reactor materials and components. A general description of the laboratory, its equipment, and its function is given. (See also WAPD-BT-3.) (W. D. M.)
- Research Organization:
- Westinghouse Electric Corp. Bettis Plant, Pittsburgh
- DOE Contract Number:
- AT-11-1-GEN-14; AND APPROPRIATE NOBS-CONTRACTS
- NSA Number:
- NSA-12-012221
- OSTI ID:
- 4321907
- Report Number(s):
- WAPD-BT-7
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-58
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ACIDITY- ALUMINUM SILICATES- CARBON STEELS- CHROMATES- CONTAMINATION- COPPER- DECONTAMINATION- EFFICIENCY- FILTERS- HYDROGEN PEROXIDES- IODINE- LEAD- LEAKS- LITHIUM COMPOUNDS- MONITORING- OXIDATION- RADIOISOTOPES- SOLUTIONS- VAN DE GRAAFF ACCELERATORS- WASTE SOLUTIONS
CANNING- CHEMICAL REACTIONS- COATING- COOLANT LOOPS- - CORROSION- DEFECTS- FUEL ELEMENTS- FUELS- MOLYBDENUM ALLOYS- OXYGEN- PELLETS- PLATING- QUANTITY RATIO- RADIATION EFFECTS- REACTORS- SINTERED MATERIALS- TEMPERATURE- TESTING- URANIUM ALLOYS- URANIUM DIOXIDE
CLEANING- COOLANTS- CORROSION- EFFICIENCY- ELECTRICITY- GASES- HEAT TREATME