Award Data

THE WORK PROPOSED IN THIS EFFORT IS DIRECTED TOWARDS DETERMINING THE CORRELATION BETWEEN OBSERVED AIRBORNE RADIOIODINE CONCENTRATIONS IN THE AUXILIARY AND FUEL HANDLING BUILDINGS AT TMI-2 FOLLOWING THE ACCIDENT IN 1979 WITH DIURNAL TEMPERATURE VARIATIONS. APPROXIMATELY 5000 MEASUREMENTS WERE MADE DURING THE PERIOD APRIL-JULY, 1979 INDESIGNATED AREAS OF THE AUXILIARY/FUEL HANDLING BUILDING AND THE ...

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STRESSES DUE TO PRESSURE AND REPEATED THERMAL CYCLING CAUSE PROGRESSIVE MATERIAL DAMAGE DURING THE OPERATION OF LWR COMPONENTS AND PIPING SYSTEMS. THE PRESENT PRO POSED RESEARCH WOULD IMPROVE THE ACCURACY OF EXISTING S- N FATIGUE EVALUATION METHODS BY COMBINING THEM WITH THE ADVANCED TECHNOLOGY OF CRACK PROPAGATION AND FRACTURE MECH ANICS. ENVIRONMENTAL EFFECTS WILL BE INCLUDED IN THE CRACK PROPAG ...

PENTEK WILL DEVELOP AND TEST A TECHNIQUE TO DETERMINE THE FUNCTIONALITY OF SOLENOID-OPERATED VALVES IN A NUCLEAR POWERPLANT BASED ON THE MEASUREMTNT AND ANALYSIS OF IN-RUSH CURRENT. THE TECHNIQUE WILL BE DEVELOPED SO THAT ALL MEASUREMENTS CAN BE MADE FROM OUTSIDE THE REACTOR BUILDING WITHOUT DISTRUBING ANY ELECTRICAL CONNECTIONS. THE ANALYSIS METHODS WILL BE DEVELOPED FOR ON-LINE USE WITH A PERSON ...

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THE OBJECTIVE OF THE PHASE I RESEARCH IS TO DETERMINE THE TECHNICAL FEASIBILITY OF THE DEVELOPMENT OF A LONG RANGE RADIOACTIVE PLUME TRANSPORT MODEL/CODE FOR THE NRC. THIS CODE WOULD BE USED TO SIMULATE THE MOVEMENT, DISPERSION, DECAY, AND DEPOSITION OF RADIONUCLIDES RELEASED FROM SEVERE NUCLEAR REACTOR ACCIDENTS, SUCH AS THE CHERNOBYL ACCIDENT. IT IS DESIRED THAT ALL RELEVANT PHYSICAL AND CHEMICA ...

THIS RESEARCH PROPOSAL DEALS WITH THE DEVELOPMENT OF A GAMMARAY DOSIMETER THAT IS BASED ON A SOLID STATE DETECTOR AND A MICROPROCERSSOR AND WILL DISPLAY THE DOSE AND DOSE RATE OF THE SKIN, AT A GIVEN DEPTH OF THE BODY OR THE BODY-AVERAGED DOSE, BY MEASURING THE SPECTRUM OF A RADIATION FIELD AND CALCULATING THE TISSUE EQAUIVALENT DOSE OF INTEREST. THE DETECTOR IS A PROPRIETARY DESIGN FEATURES OF TH ...

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STEAM GENERATOR TUBES REPRESENT A UNIQUE PART OF THE REACTOR COOLANT SYSTEM (RCS). LEAKAGE FROM ANY OTHER PART OF THE RCS IS CAPTURED BY THE CONTAINMENT BUILDING, BUT STEAM GENERATOR TUBE LEAKAGE IS TRANSPORTED OUT OF THE CONTAINMENT BUILDING ALONG WITH THE STEAM, WHICH IS NORMALLY UNCONTAMINATED. STEAM GENERATOR TUBES, CONSEQUENTLY, DESERVE, AND RECEIVE SPECIAL CONSIDERATION. THE ASSURANCE OF STE ...

ON FEBRUARY 9, 1991, AT THE MIHAMA UNIT 2 NUCLEAR POWER STATION, OPEARTED BY KANSAI ELECTRIC CORPORATION, A STEAM GENERATOR TUBE RUPTURED AND RELEASED APPROXIMATELY 9,000 GALLONS OF REACTOR COOLANT INTO THE SECONDARY SYSTEM. THE LEAKAGE CAUSED A RAPID DEPRESSURIZATION OF THE REACTOR COOLANT SYSTEM, WHICH RESULTED IN AN AUTOMATIC REACTOR TRIP AND ACTUATION OF THE HIGH PRESSURE SAFETY INJECTION SYST ...