You are here

Award Data

For best search results, use the search terms first and then apply the filters
Reset

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

    N/A

    SBIR Phase I 1988 Nuclear Regulatory Commission
  2. RISK-BASED ANALYSIS OF TECHNICAL SPECIFICATIONS

    SBC: Applied Biomathematics Inc            Topic: N/A

    THE FRANTIC COMPUTER CODE IS THE MOST ADVANCED MODEL FOR ADDRESSING TIME-DEPENDENT RISK EFFECTS ASSOCIATED WITH TECHNICAL SPECIFICATIONS. IT IS USED BY THE INDUSTRY FOR THE EVALUATION OF UPGRADES AND/OR IMPROVEMENTS IN EXISTING TECHNICAL SPECIFICATIONS AND BY THE NRC STAFF IN RESPONDING TO THE LICENSEE SUBMITTALS. THE EXISTING METHODOLOGY HAS TWO MAJOR DEFICIENCIES: IT DOES NOT PROVIDE THE BOUNDIN ...

    SBIR Phase II 1988 Nuclear Regulatory Commission
  3. 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
  4. SEISMIC PRA

    SBC: Future Resources Associate Inc            Topic: N/A

    N/A

    SBIR Phase I 1983 Nuclear Regulatory Commission
  5. VALIDATION & TESTING OF THE VAM2D COMPUTER CODE

    SBC: Hydrogeologic Inc.            Topic: N/A

    N/A

    SBIR Phase I 1988 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

    N/A

    SBIR Phase I 1988 Nuclear Regulatory Commission
  9. PREDICTION OF CHECK VALVE PERFORMANCE & DEGRADATION IN NUCLEAR POWER PLANT SYSTEMS

    SBC: Kalsi Engineering, Incorporated            Topic: N/A

    THIS PROJECT IS AIMED AT DEVELOPING TECHNIQUES FOR PREDICTING CHECK VALVE PERFORMANCE AND ITS INTERNAL COMPONENTS DEGRADATION IN PRACTICAL PIPING SYSTEMS USED IN NUCLEAR POWER PLANTS. THE MAIN FOCUS OF THE EFFORT IS TO SYSTEMATICALLY EVALUATE THE EFFECT OF UPSTREAM DISTURBANCES WHICH ARE WITHIN 10 DIAMETERS UPSTREAM. BY USING A COMBINED THEORETICAL AND EXPERIMENTAL APPROACH, GENERALIZED NONDIMENSI ...

    SBIR Phase II 1988 Nuclear Regulatory Commission
  10. PRESSURIZED WATER REACTOR TRANSIENT ANALYSIS MODEL

    SBC: Levy S Inc            Topic: N/A

    N/A

    SBIR Phase I 1983 Nuclear Regulatory Commission
US Flag An Official Website of the United States Government