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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. EFFECT OF AGING ON RESPONSE TIME OF NUCLEAR PLANT PRESSURE SENSORS

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

    PERIODIC RESPONSE TIME TESTING HAS BEEN PERFORMED FOR THE PAST TWELVE YEARS ON THE SAFETY SYSTEM PRESSURE SENSORS IN MANY NUCLEAR POWER PLANTS. HOWEVER, THE RESULTS OF THESE TESTS ARE NOT RELIABLE FOR ASSESSMENT OF AGING EFFECTS. THEIS BECAUSE INADEQUATE METHODS AND PROCEDURES HAVE BEEN USED IN PERFORMING THE MAJORITY OF THE TESTS. THIS PROPOSAL OFFFERS AN EXPERIMENTAL RESEARCH PROJECT TO PROVIDE ...

    SBIR Phase II 1989 Nuclear Regulatory Commission
  2. BWR RECIRCULATION INLET SAFE ENDS-A THREAT TO PLANT LIFE ANDSAFETY

    SBC: Aptech Engineering Services            Topic: N/A

    AN ON-GOING THREAT TO THE RESIDUAL LIFETIME AND SAFETY OF BOILING WATER REACTORS (BWRS) IS INTERGRANULAR STRESS CORROSION CRACKING (IGSCC). A COMPONENT OF SPECIAL CONCERN IN THE RECIRCULATION INLET NOZZLE SAFE END (RINSE). FOR EXAMPLE, WITHIN THE LAST 2 YEARS 30 OUT OF 30 RINSES ARE KNOWN TO BE CRACKED AT A 3-UNIT BWR SITE AND IT IS BELIEVED THAT 20 OUT OF 20 RINSES ARE CRACKED AT A 2-UNIT BWR SIT ...

    SBIR Phase I 1989 Nuclear Regulatory Commission
  3. SEISMIC PRA

    SBC: Future Resources Associate Inc            Topic: N/A

    N/A

    SBIR Phase I 1983 Nuclear Regulatory Commission
  4. USE OF CERAMIC FUEL CLADDING TO REDUCE THE SEVERITY OF LMR ACCIDENTS

    SBC: Gamma Engineering Corporation            Topic: N/A

    THIS PROJECT INVESTIGATES THE FEASIBILITY OF USING CERAMIC CLADDING MATERIALS TO REPLACE THE METALLIC CLADDING MATERIALS NOW USED WITH WATER REACTOR FUEL. SHOULD FEASIBILITY BE DETERMINED, AND EVENTUALLY COMMERCIALIZED, THE ABILITY OF WATER REACTORS TO WITHSTAND SEVERE ACCIDENTS WOULD BE ENHANCED. WITH TODAYS METAL CLAD FUEL, A RELATIVELY SHORT TIME PERIOD IS AVAILABLE AFTER A LOSS OF COOLANT ACCI ...

    SBIR Phase I 1989 Nuclear Regulatory Commission
  5. VALIDATION & TESTING OF THE VAM2D COMPUTER CODE

    SBC: Hydrogeologic Inc.            Topic: N/A

    SEVERAL STATES ARE CURRENTLY SEEKING MUCH-NEEDED NEW LOW-LEVEL RADIOACTIVE DISPOSAL SITES IN ACCORDANCE WITH THE LOW-LEVEL RADIOACTIVE WASTE POLICY ACT OF 1980. ANY NEW COMMERCIALREQUIREMENT THAT A SITE BE CAPABLE OF BEING MODELED AND THATITS PERFORMANCE BE ASSURED FOR 500 YEARS. FOR MOST SITES, THE HYDROGEOLOGICAL AND RADIONUCLIDE TRANSPORT CHARACTERIS- TICS OF THE UNSATURATED ZONE ARE MAJOR FACT ...

    SBIR Phase II 1989 Nuclear Regulatory Commission
  6. 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
  7. 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
  8. DEV OF A LARGE CROSS SECTIONAL AREA SELF-POWERED DETECTOR

    SBC: K E M P CORP            Topic: N/A

    A SELF-POWERED RADIATION DETECTOR THAT CAN BE USED TO DETECTTHE SOURCE POSITION IN INDUSTRIAL RADIOGRAPHIC EQUIPMENT IS NEEDED. SELF-POWERED DETECTORS HAVE TRADITIONALLY BEEN USEDINFLUX MAPPING SYSTEMS IN NUCLEAR REACTORS BECAUSE OF THEIR SIZE, RUGGEDNESS AND SIMPLICITY. THIS DETECTOR CONCEP PROVIDES THE UNIQUE OPPORTUNITY FOR THE DEVELOPMENT OF LARGECROSS SECTIONAL AREA DETECTORS THATCAN BE USED ...

    SBIR Phase II 1989 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. 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
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