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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. ASSESSMENT OF RARE EVENT FREQUENCIES OFTEN REQUIRES SIGNIFI-CANT RELIANCE ON EXPERT JUDGEMENT DUE TO THE SCARCITY OF EMPIRICAL DATA.

    SBC: Pickard, Lowe & Garrick Inc.            Topic: N/A

    ASSESSMENT OF RARE EVENT FREQUENCIES OFTEN REQUIRES SIGNIFI-CANT RELIANCE ON EXPERT JUDGEMENT DUE TO THE SCARCITY OF EMPIRICAL DATA. IN THIS WORK, FORMAL MODELS FOR USING THE OPINIONS OF SINGLE AND MULTIPLE EXPERTS WILL BE EVALUATED INLIGNT OF EMPIRICAL DATA. THE OBJECTIVE IS TO SEE TO WHAT EXTENT THE EMPIRICAL DATA "VALIDATES" THE EXPERTS' ESTIMATES, AS WELL AS THE MODELS USED FOR ANALYZING SUCH ...

    SBIR Phase I 1986 Nuclear Regulatory Commission
  3. A TEST METHOD FOR RELIAVLY AND EASILY EVALUATING THE CONDITION OF A REACTOR COOLANT PUMP (RCP) SHAFT WHEN THER E IS ONLY LIMITED ACCESS TO THE SHAFT AT THE COUPLING WOULD ENABLE THE NUCLEAR INDUSTRY TO EVALUATE THESE SHAFT SYSTEMS ON SITE.

    SBC: Rem Technologies Inc.            Topic: N/A

    A TEST METHOD FOR RELIAVLY AND EASILY EVALUATING THE CONDITION OF A REACTOR COOLANT PUMP (RCP) SHAFT WHEN THER E IS ONLY LIMITED ACCESS TO THE SHAFT AT THE COUPLING WOULD ENABLE THE NUCLEAR INDUSTRY TO EVALUATE THESE SHAFT SYSTEMS ON SITE. THIS PROJECT PROVIDES A TESTING METHOD WHICH CAN BEAPPLIED TO IDENTIFY THE PRESENCE, SIZE, AND LOCATION OF SHAFT CRACKS IN A VERTICAL RCP SHAFT SYSTEM. CONFIRMA ...

    SBIR Phase I 1986 Nuclear Regulatory Commission
  4. BASED ON HEAT RELEASE MONITORING: A DEMONSTRATION PROGRAM

    SBC: Geoscience Ltd            Topic: N/A

    THE PROPOSED PROGRAM CONSISTS OF THE DEVELOPMENT OF A TECHNIQUE AND A SYSTEM TO MEASURE THE RADIOACTIVE DECAY OF OF RADWASTE CONTAINED IN STORAGE CANISTERS, CASKS AND VAULTS. THE SYSTEM BEING CONSIDERED DEALS WITH THE DIRECT MEASUREMENT OF THE AFTERHEAT BEING GENERATED IN THE RADWASTEVOLUMES. THE SYSTEM TO BE USED TO ACCOMPLISH SUCH MEASURE MENTS CONSISTS OF A HEAT FLUX SENSOR ENVELOPE THAT SURROU ...

    SBIR Phase I 1986 Nuclear Regulatory Commission
  5. 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
  6. 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
  7. DEGRATION OF NUCLEAR PLANT TEMPERATURE SENSORS

    SBC: ANALYSIS AND MEASUREMENT SERVICES CORPORATION            Topic: N/A

    N/A

    SBIR Phase I 1986 Nuclear Regulatory Commission
  8. EXTENDED FATIGUE LIFE EVALUATION METHODS FOR AGED LWR COMPONENTS

    SBC: O'donnell Consulting Engineers            Topic: N/A

    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 ...

    SBIR Phase II 1986 Nuclear Regulatory Commission
  9. 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
  10. FUNCTIONAL CONDITION OF SOLENOID-OPERATED VALVES USED IN NUCLEAR POWER PLANT SAFETY APPLICATIONS

    SBC: Pentek Inc.            Topic: N/A

    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 ...

    SBIR Phase I 1986 Nuclear Regulatory Commission
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