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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. AN ULTRA-HIGH SPEED RESIDUE NUMBER PROCESSOR FOR SAFT INSPECTION SYSTEM IMAGE ENHANCEMENT

    SBC: Sigma Research Corp            Topic: N/A

    N/A

    SBIR Phase I 1983 Nuclear Regulatory Commission
  2. COMBINING LASER MEASUREMENTS WITH BACKWARD WAVE TECHNIQUES FOR EVALUATION OF UNDERGROUND OPENINGS IN OIL SHALE

    SBC: Sigma Research Corp            Topic: N/A

    N/A

    SBIR Phase I 1983 Nuclear Regulatory Commission
  3. COMMON CAUSE FAILURE ANALYSIS (CCFA) IS AN IMPORTANT ELEMENTOF A COMPLETE PROBABILISTIC RISK ASSESSMENT (PRA) SINCE COMMON CAUSE FAILURE IS OFTEN A DOMINANT FACTOR IN THE RISK POSED TO PUBLIC HEALTH AND SAFETY FROM NUCLEAR POWER PLANT ACCIDENTS.

    SBC: Jfb Associates Inc.            Topic: N/A

    COMMON CAUSE FAILURE ANALYSIS (CCFA) IS AN IMPORTANT ELEMENTOF A COMPLETE PROBABILISTIC RISK ASSESSMENT (PRA) SINCE COMMON CAUSE FAILURE IS OFTEN A DOMINANT FACTOR IN THE RISK POSED TO PUBLIC HEALTH AND SAFETY FROM NUCLEAR POWER PLANT ACCIDENTS. A MAJOR PROBLEM ASSOCIATED WITH PERFORMING A CFFA IS THE ABSENCE OF SUPPORTING QUALITATIVE OR QUANTITATIVE COMPONENT FAILURE DATA. EXTENSIVE AMOUNTS OF CO ...

    SBIR Phase I 1983 Nuclear Regulatory Commission
  4. FOLLOWING A POST-IRRADIATION THERMAL ANNEAL CYCLE

    SBC: Materials Engineering &            Topic: N/A

    THIS RESEARCH WILL DETERMINE THE CHARACTERISTICS OF FATIGUE INITIATION LIFE, FATIGUE CRACK GROWTH RATES, AND SLOW-STABLECRACK EXTENSIONS FOLLOWING A POST-IRRADIATION ANNEAL. FATIGUE INTITIATION LIFE WILL BE DETERMINED WITH SMOOTH SPECIMENS OF 308 STAINLESS STEEL WHICH HAVE BEEN ANNEALED AND THEN CYCLED IN PRESSURIZED, HIGH-TEMPERATURE WATER. SUBMERGED ARC WELD STEEL (LINDE 80 FLUX) WILL BE PARTIAL ...

    SBIR Phase I 1983 Nuclear Regulatory Commission
  5. N/A

    SBC: Datasonics, Inc.            Topic: N/A

    THERE IS A NEED FOR DEVELOPMENT OF A COMMERCIALLY AVAILABLE ECONOMICAL ACOUSTIC DOPPLER BACKSCATTER INSTRUMENT WHICH CANBE EASILY DEPLOYED AND USED TO SIMULTANEOUSLY ACQUIRE CURRENT PROFILE DATA AND BACKSCATTER AMPLITUDE INFORMATION RELATING TO PARTICLE CONCENTRATIONS IN THE WATER COLUMN. THE RESEARCH PROPOSED IN PHASE I IS DIRECTED AT TWO AREAS OFDOPPLER BACKSCATTER MEASUREMENT WHERE ADVANCES IN ...

    SBIR Phase I 1983 Department of the Interior
  6. N/A

    SBC: STARFIRE ENGINEERING INC.            Topic: N/A

    WHEN IT IS NECESSARY TO RAISE A MARINE PIPELINE FOR REPAIR DUE TO TRAWLER SNAG, ETC., THE PIPELINE WILL BUCKLE, AND THEN THE BUCKLE WILL PROPAGATE IF ALL CONDITIONS ARE NOT PROPER. WITH SEVERE BUCKLES, THE PIPE WILL BREAK OPEN ALLOWING THE OIL TO SPILL. THIS CAN BE MINIMIZED BY PERIODICALLY PLACING REMOTELY OPERABLE VALVES IN THE LINE FOR CUTOFF. BUT SOMETIMES THE PIPELINE ROTATES AS IT IS BEING L ...

    SBIR Phase I 1983 Department of the Interior
  7. N/A

    SBC: TRADCO CHEMICAL CORPON            Topic: N/A

    USING RADIO TELEMETRY MODEMS, IS CURRENTLY POSSIBLE. THIS IS NECESSARY BECAUSE LACK OF MONITORING CAUSES INADEQUATE CONTROL OF INTERNAL CORROSION TAKING PLACE INSIDE OFFSHORE PIPELINE SYSTEMS. THE NET RESULT IS PIPELINE FAILURE DUE TOTHE EFFECTS OF CORROSION. THE RESULT OF PIPELINE FAILURE WILL BE AN OIL SPILL IN COASTAL WATERS. AS THE NATION'S OFFSHORE PIPELINE SYSTEM GROWS OLDER, THE NET EFFECTS ...

    SBIR Phase I 1983 Department of the Interior
  8. OF REACTOR THERMAL-HYDRAULICS CODES.

    SBC: International Energy            Topic: N/A

    OF REACTOR THERMAL-HYDRAULICS CODES. THESE CODES HAVE INTERNATIONAL APPLICABILITY. TRADING THESE CODES, WITH APPROPRIATE SUPPORT, TO OTHER COUNTRIES IN EXCHANGE FOR USEFUL DATA OR OTHER RESOURCES WOULD ENHANCE THEIR UTILITY AND REDUCE THE COST TO THE U.S. OF GENERATING EQUIVALENT DATA. THE OBJECTIVE OF THE PROPOSED EFFORT IS TO PROVIDE A SOUND TECHNICAL BASIS FOR SUCH AN EXCHANGE BY: IDENTIFYING C ...

    SBIR Phase I 1983 Nuclear Regulatory Commission
  9. PRESSURIZED WATER REACTOR TRANSIENT ANALYSIS MODEL

    SBC: Levy S Inc            Topic: N/A

    N/A

    SBIR Phase I 1983 Nuclear Regulatory Commission
  10. ROBOTICS APPLICATION FOR EXPOSURE REDUCTION

    SBC: Remotec Inc.            Topic: N/A

    N/A

    SBIR Phase I 1983 Nuclear Regulatory Commission
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