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Award Data

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The Award database is continually updated throughout the year. As a result, data for FY24 is not expected to be complete until March, 2025.

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.

The SBIR.gov award data files now contain the required fields to calculate award timeliness for individual awards or for an agency or branch. Additional information on calculating award timeliness is available on the Data Resource Page.

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

    SBC: ANALYSIS AND MEASUREMENT SERVICE 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. 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
  4. 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
  5. 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
  6. IMPROVED MODEL FOR PREDICTING J-R CURVES FROM CHARPY DATA

    SBC: Modeling & Computing Services            Topic: N/A

    IT IS NECESSARY TO ESTIMATE J-R OR JI DATA FOR AGING AND RE-SIDUAL LIFE STUDIES, USING DATA FROM SURVEILLANCE CAPSULE SPECIMENS THAT REFLECT THE CURRENT STATE OF THE PRESSURE VESSEL STEEL. AN IMPROVED MODEL IS NEEDED THAT WILL PREDICT J J-R DATA FROM CHARPY DATA, TENSILE PROPERTIES, MATERIAL COM-POSITION AND OTHER MEASURABLE PROPERTIES. SUCH A MODEL WILLBE DEVELOPED UNDER THIS PROJECT, USING INNOV ...

    SBIR Phase II 1989 Nuclear Regulatory Commission
  7. DEVELOPMENT OF A REAL TIME LONG RANGE RADIOACTIVE PLUME TRANSPORT SIMULATION MODEL

    SBC: PHYSICAL RESEARCH, INC.            Topic: N/A

    THE FEASIBILITY OF DEVELOPMENT OF A NEW LONG RANGE RADIOACTIVE PLUME TRANSPORT CODE IS PROPOSED. NEW APPROACHES TO ESTIMATE THE RADIOACTIVE DECAY, WET AND DRY DEPOSITION, PARTICULATE COAGULATION, AND ATMOSPHERIC PARAMETERS WILL BE EXPLORED AND A SIMPLE, IDEALIZED EVALUATION OF THESE ALGORITHMS WILL BE MADE IN PHASE I OF THE PROPOSED EFFORT. BASED ON THESE STUDIES A) AN APPROPRIATE NEAR SOURCE RISE ...

    SBIR Phase I 1989 Nuclear Regulatory Commission
  8. TWO NEW NDE TECHNIQUES FOR INSPECTION OF CONTAINMENT WELDS BENEATH COATINGS

    SBC: PHYSICAL RESEARCH, INC.            Topic: N/A

    N/A

    SBIR Phase I 1989 Nuclear Regulatory Commission
  9. QUANTIFICATION OF CONSERVATISMS IN SEISMIC RISK ESTIMATES THROUGH ENGINEERING ADVANCEMENT OF SEISMIC PRA

    SBC: Risk Engineering Inc.            Topic: N/A

    N/A

    SBIR Phase I 1989 Nuclear Regulatory Commission
  10. MICRO COMPUTER BASED PARALLEL PROCESSING SYSTEM FOR CODE COMPUTATIONS

    SBC: Risk Management Systems            Topic: N/A

    THE RESEARCH PROGRAM WILL DEVELOP A MICROCOMPUTER BASED SYSTEM OF HARDWARE AND SOFTWARE WHICH WILL ALLOW THE USER TOEXECUTE MAINFRAME BASED CODES ON THE MICROCOMPUTER. IN ADDITION PARALLEL EXECUTION OF SEVERAL CODES AT ONCE IS POSSIBLEA SPECIAL INPUT AND OUTPUT PROCESSOR MODULES WILL ALSO BE DEVELOPED TO DEMONSTRATE THE USER FRIENDLY CAPABILITIES OF THE SYSTEM AND FACILITATE INPUT PREPARATION AND ...

    SBIR Phase II 1989 Nuclear Regulatory Commission
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