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The Award database is continually updated throughout the year. As a result, data for FY21 is not expected to be complete until September, 2022.

Download all SBIR.gov award data either with award abstracts (290MB) or without award abstracts (65MB). A data dictionary and additional information is located on the Data Resource Page. Files are refreshed monthly.

  1. Inservice Diagnostics of Motor Operated Valves

    SBC: ACENTECH INCORPORATED            Topic: N/A

    N/A

    SBIR Phase II 1996 Nuclear Regulatory Commission
  2. A Detection System for Determining the Concentration, Size, and Depth of Buried Radioactive Material

    SBC: Shonka Research Associates            Topic: N/A

    N/A

    SBIR Phase II 1996 Nuclear Regulatory Commission
  3. SPECIAL MONITOR DETECTOR DEVELOPMENT FOR RESPIRATOR CONTAMINATION

    SBC: Shonka Research Associates            Topic: N/A

    IMPLEMENTATION OF AN INTEGRATED DETECTION SYSTEM FOR CONTAMINATION MONITORING OF RESPIRATORS HAS BEEN PROBLEMATIC. BECAUSE OF THE COMPLEX SURFACES, HAND MONITORING USING PORTABLE SURVEY INSTRUMENTATION HAS BEEN THE PREFERRED METHOD. HAND MONITORING IS COSTLY IN TIME AND OFTEN FAILS TO RELIABLY ACHIEVE A GIVEN DETECTION LIMIT BECAUSE OF VARIABLES SUCH AS SURVEY SPEED ANDDISTANCE FROM THE PROBE. THE ...

    SBIR Phase II 1994 Nuclear Regulatory Commission
  4. A PORTABLE IMAGING SYSTEM FOR NONDESTRUCTIVE EXAMINATION OF NUCLEAR POWER PLANT COMPONENTS

    SBC: TPL, Inc            Topic: N/A

    THE DIFFICULTY IN PREDICTING STRUCTURAL DEGRADATION RATES FOR NUCLEAR POWER PLANT COMPONENTS DUE TO CORROSION AND OTHER FACTORS HAS LED TO THE NEED FOR COSTLY, TIME CONSUMING INSPECTIONS AND INCREASED COST FROM INTENTIONALLY OVERDESIGNED COMPONENTS. THE SITUATION INDICATES A SERIOUS, UNMET NEED FOR A SIMPLE BUT ACCURATE SYSTEM FOR REAL- TIME, IN SITU, NONDESTRUCTIVE ANALYSIS OF NUCLEAR POWER PLANT ...

    SBIR Phase II 1994 Nuclear Regulatory Commission
  5. WORK UNDERLOAD IN MODERN NPP CIBTRIK ROOMS

    SBC: UES, Inc.            Topic: N/A

    THE PROBLEM ADDRESSED IS THAT FUTURE NUCLEAR POWER PLANT CONTROL ROOM OPERATOR WORKLOAD WILL CONSIST PRIMARILY OF PASSIVE MONITORING FOR EXTENDED PERIODS OF TIME. THIS WILL RESULT IN DIFFICULTY MAINTAINING OPERATOR ALERTNESS AND PERFORMANCE CAPABILITY. THE TWO OBJECTIVES OF THIS PROJECT ARE TO PROVIDE THE CAPABILITY TO PREDICT AND EVALUATE THE EFFECT OF WORK UNDERLOADON HUMAN PERFORMANCE IN NPP CO ...

    SBIR Phase II 1994 Nuclear Regulatory Commission
  6. ENHANCED REMOVAL OF RADIOACTIVE PARTICLES BY FLUOROCARBON SURFACTANT SOLUTIONS

    SBC: Entropic Systems, Inc.            Topic: N/A

    N/A

    SBIR Phase I 1992 Nuclear Regulatory Commission
  7. ENHANCEMENT TO STEAM GENERATOR TUBING EDDY CURRENT INSPECTION BY APPLICATION OF THERMALLY INDUCED STRESSES

    SBC: FOSTER-MILLER, INC.            Topic: N/A

    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 ...

    SBIR Phase I 1992 Nuclear Regulatory Commission
  8. NONDESTRUCTIVE EXAMINATION TO DIRECTLY MEASURE STEAM GENERATOR TUBE U-BEND VIBRATORY RESPONSE

    SBC: FOSTER-MILLER, INC.            Topic: N/A

    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 ...

    SBIR Phase I 1992 Nuclear Regulatory Commission
  9. EVALUATION OF GENERAL FAILURE TYPES IN SAFETY ANALYSIS

    SBC: John Wreathall & Company            Topic: N/A

    THIS WORK IS TO DEVELOP A METHOD TO IMPROVE THE ABILITY OF THE USNRC TO EVALUATE THE OPERATIONAL SAFETY SIGNIFICANCE OF OCCURANCES AT NUCLEAR POWER PLANTS. PERHAPS THE AREA OF GREATEST SAFETY SIGNIFICANCE IS HUMAN PERFORMANCE, BUT THE TECHNIQUES USED BY NRC DO NOT EVALUATE HUMAN PERFORMANCE IN ANY SYSTEMIC WAY. THE WORK IS PROPOSED TO BE PERFORMED IN THREE STAGES, AND BUILDS ON METHODS THAT HAVE B ...

    SBIR Phase I 1992 Nuclear Regulatory Commission
  10. DETECTION OF INCIPIENT CORROSION IN NUCLEAR POWER PLANTS

    SBC: MASSACHUSETTS TECHNOLOGICAL LABORATORY            Topic: N/A

    ACOUSTIC FIELDS CAN BE DESIGNED TO COAX LIQUID BORNE SUBMICRONIC PARTICLES TO ANNOUNCE THEIR PRESENCE LOUDER THAN THE USUAL SCATTERING SIGNALS WHICH ARE PRIMARILY DETERMINED BY THE DENSITY AND COMPRESSIBILITY CONTRAST BETWEEN THE PARTICLE MATERIAL AND THE HOST FLUID. WE EXPECT A SIGNAL ENHANCEMENT OF AT LEAST 60DB. THE KEY CONCEPT IS TO COAX THE PARTICLES TO SOFT CAVITATE AND DETECT THE ENSUING TR ...

    SBIR Phase I 1992 Nuclear Regulatory Commission
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