List

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 the given year is not complete until April of the following year. Annual Reports data is a snapshot of agency reported information for that year and hence might look different from the live data in the Awards Information charts.

  1. SEISMIC PRA

    SBC: Future Resources Associate Inc            Topic: n/a

    N/A

    SBIR Phase I 1983 Nuclear Regulatory Commission
  2. 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
  3. 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
  4. PRESSURIZED WATER REACTOR TRANSIENT ANALYSIS MODEL

    SBC: Levy S Inc            Topic: n/a

    N/A

    SBIR Phase I 1983 Nuclear Regulatory Commission
  5. 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
  6. STUDY ON AVAILABILITY AND COMPOSITION OF METAL BEARING WASTES

    SBC: N.h. Parker, P.e. And            Topic: n/a

    N/A

    SBIR Phase I 1983 Nuclear Regulatory Commission
  7. ROBOTICS APPLICATION FOR EXPOSURE REDUCTION

    SBC: Remotec Inc.            Topic: n/a

    N/A

    SBIR Phase I 1983 Nuclear Regulatory Commission
  8. 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
  9. 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

Agency Micro-sites

SBA logo
Department of Agriculture logo
Department of Commerce logo
Department of Defense logo
Department of Education logo
Department of Energy logo
Department of Health and Human Services logo
Department of Homeland Security logo
Department of Transportation logo
Environmental Protection Agency logo
National Aeronautics and Space Administration logo
National Science Foundation logo
US Flag An Official Website of the United States Government