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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. 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
  2. Extending the Dynamic Flowgraph Methodology (DFM) to Model Human Performance and Team Effects

    SBC: ASCA, INC.            Topic: N/A

    N/A

    SBIR Phase II 1996 Nuclear Regulatory Commission
  3. Development of Self-Repairing Concrete Containers of Radioactive Waste Using Superelastic Reinforcement

    SBC: DPD, Inc.            Topic: N/A

    N/A

    SBIR Phase II 1996 Nuclear Regulatory Commission
  4. SEISMIC PRA

    SBC: Future Resources Associate Inc            Topic: N/A

    TECHNIQUES HAVE RECENTLY BEEN DEVELOPED FOR PROBABILISTIC ANALYSIS OF THE RISK FROM EARTHQUAKE-INITIATED ACCIDENTS AT NUCLEAR POWER REACTORS. THESE TECHNIQUES ARE NOW BEGINNING TO BE APPLIED AS PARTS OF LARGER PRA STUDIES. HOWEVER, THE RESULTS OF APPLYING THESE SEISMIC PRA TECHNIQUES ARE STILL HIGHLY UNCERTAIN, AND THE INSIGHTS GAINED SO FAR FOR SPECIFIC REACTORS ARE DIFFICULT TO GENERALIZE. THIS ...

    SBIR Phase II 1984 Nuclear Regulatory Commission
  5. EVAL OF RELIABILITY & USEFULNESS OF EXTERNAL-INITIATOR PRA METHODOLOGIES

    SBC: Future Resources Associate Inc            Topic: N/A

    THE DISCIPLINE OF EXTERNAL-INITIATOR PRA ANALYSIS IS RELA- TIVELY LESS MATURE AND LESS RELIABLE THAN THE CORRESPONDING INTERNAL-INITIATORS PRA ANALYSIS. THESE RELATIVE WEAKNESSESHAVE MADE MANY DECISION-MAKERS, IN BOTH INDUSTRY AND THE NRCRELUCTANT TO USE EXTERNAL-INITIATOR PRA RESULTS. THE EXTER-NAL-INITIATOR ANALYSES HAVE BEEN CONSIDERED TOO UNCERTAIN, OR TOO CONSERVATIVE, OR SUPPORTED BY TOO LIT ...

    SBIR Phase I 1988 Nuclear Regulatory Commission
  6. SCOPING ANALYSIS OF LWR SHUTDOWN ACCIDENTS INITIATED BY EARTHQUAKES AND INTERNAL FIRES

    SBC: Future Resources Associate Inc            Topic: N/A

    N/A

    SBIR Phase I 1990 Nuclear Regulatory Commission
  7. 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
  8. VALIDATION & TESTING OF THE VAM2D COMPUTER CODE

    SBC: Hydrogeologic Inc.            Topic: N/A

    N/A

    SBIR Phase I 1988 Nuclear Regulatory Commission
  9. PRESSURIZED WATER REACTOR TRANSIENT ANALYSIS MODEL

    SBC: Levy S Inc            Topic: N/A

    THIS PROPOSAL DESCRIBES A PROGRAM FOR THE DEVELOPMENT OF A PRESSURIZED WATER REACTOR (PWR) TRANSIENT ANALYSIS MODEL FOR USE ON A MICROCOMPUTER. THE INTENDED APPLICATION OF THIS PWR MODEL IS FOR ANALYSIS OF PWR SYSTEM RESPONSE, INCLUDING FORCED AND NATURAL CIRCULATION OPERATION. THE PRIMARY USER OF SUCH A MODEL WOULD BE A UTILITY OR NUCLEAR REGULATORY COMMISSION (NRC) ENGINEER OR PLANT OPERATOR PER ...

    SBIR Phase II 1984 Nuclear Regulatory Commission
  10. PROBABILITY OF FLOODS WITH VERY LONG RETURN PERIODS

    SBC: Linsley Kraeger Associates Ltd            Topic: N/A

    N/A

    SBIR Phase I 1984 Nuclear Regulatory Commission
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