Award Data

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The Award database is continually updated throughout the year. As a result, data for FY19 is not expected to be complete until September, 2020.

  1. A FUZZY SET APPROACH FOR SEISMIC SAFETY MARGINS ASSESSMENT.

    SBC: Eda Consultants            Topic: N/A

    THE CONTRACTOR SHALL DEVELOP A FUZZY SET METHODOLOGY FOR UNCERTAINTY ANALYSIS IN PROBABILISTIC SEISMIC SAFETY ASSESSMENT OF NUCLEAR POWER PLANTS. FUZZY SET LOGIC WILL BEUSED FOR COLLECTING, QUANTIFYING AND PROPAGATING SUBJECTIVE,ENGINEERING JUDGEMENT USED IN THE UNCERTAINTY ANALYSIS. IN PHASE I, FEASIBILITY OF THE PROPOSED APPROACH WILL BE DEMONSTRATED BY APPLYING IT TO SELECTED PARTS OF A PROBABI ...

    SBIR Phase I 1987 Nuclear Regulatory Commission
  2. Countermeasures to Covert Access Methods to Reduce Attack Susceptibility and Ensure Trust (

    SBC: SICORE TECHNOLOGIES INC.            Topic: OSD09IA1

    Our proposed approach to computer security is proactive. We collect data through a set of sensors which is used to adapt to an attack, while protecting the operational integrity of the system under its protection.

    SBIR Phase II 2011 Department of DefenseOffice of the Secretary of Defense
  3. DEVELOP AN INHALATION SCREENING DOSE MONITOR FOR WORKERS AT NUCLEAR POWER PLANTS

    SBC: Mikayola International            Topic: N/A

    AN "INHALATION SCREENING DOSE COLLAR-STANCHION MONITOR" WITHEMBEDDED MINIATURE THIN-WALL GEIGER-MUELLER RADIATION DETECTORS EVALUATES THE THYROID GLAND FOR NANOCURIE ACTIVITYINVENTORY. THE PRIMARY TECHNICAL OBJECTIVE IS TO ESTABLISH THAT THE "COLLAR-STANCHION MONITOR" WILL BE CAPABLE OF DETECTING WITHIN 15 SECONDS AND WITH 2 SIGMA CONFIDENCE AN ACTIVITY INVENTORY OF 0.7 NANOCURIES OF I-131 DOSE EQ ...

    SBIR Phase I 1987 Nuclear Regulatory Commission
  4. 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
  5. PREDICTION OF CHECK VALVE PERFORMANCE & DEGRADATION IN NUCLEAR POWER PLANT SYSTEMS

    SBC: Kalsi Engineering, Incorporated            Topic: N/A

    N/A

    SBIR Phase I 1987 Nuclear Regulatory Commission
  6. 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
  7. RISK-BASED ANALYSIS OF TECHNICAL SPECIFICATIONS

    SBC: Applied Biomathematics Inc            Topic: N/A

    N/A

    SBIR Phase I 1987 Nuclear Regulatory Commission
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