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Award Data

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The Award database is continually updated throughout the year. As a result, data for FY20 is not expected to be complete until September, 2021.

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 I 1995 Nuclear Regulatory Commission
  2. AN YTTRIUM ALUMINUM PEROVSKITE BASED GAMMA-RAY DOSIMETER

    SBC: W Peter Trower Inc.            Topic: N/A

    N/A

    SBIR Phase I 1994 Nuclear Regulatory Commission
  3. 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
  4. 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
  5. 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
  6. 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
  7. VALIDATION & TESTING OF THE VAM2D COMPUTER CODE

    SBC: Hydrogeologic Inc.            Topic: N/A

    N/A

    SBIR Phase I 1988 Nuclear Regulatory Commission
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