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The Award database is continually updated throughout the year. As a result, data for FY20 is not expected to be complete until September, 2021.

  1. DEVELOPMENT OF A DYNAMIC OPERATIONAL RISK MODEL TO SUPPORT RISK MANAGEMENT OF NUCLEAR POWER PLANTS

    SBC: Accident Prevention Group            Topic: N/A

    CURRENT ACTIVITY WITHIN THE NRC AND THE NUCLEAR INDUSTRY SEEKS TO EXPLOIT THE BENEFITS OF PRA IN RISK-BASED APPROACHES TO RELIEVE REGULATORY BURDEN ON THE ECONOMICALLY THREATENED NUCLEAR POWER PLANTS. THE ACCIDENT PREVENTION GROUP HAS BEEN DEVELOPING THE CONCEPT OF AN INTEGRATED RISK MANAGEMENT PROGRAM (IRMP) TOWARD SUCH GOALS. A KEY ELEMENT OF AN IRMP IS AN "OPERATIONAL RISK MODEL" OF THE NPP THA ...

    SBIR Phase I 1994 Nuclear Regulatory Commission
  2. COMPUTERIZED EMERGENCY OPERATION PROCEDURES RESEARCH

    SBC: Accident Prevention Group            Topic: N/A

    N/A

    SBIR Phase I 1992 Nuclear Regulatory Commission
  3. Integrated Risk Management and Quality Assurance

    SBC: Accident Prevention Group            Topic: N/A

    N/A

    SBIR Phase I 1995 Nuclear Regulatory Commission
  4. AN ADAPTING FINITE ELEMENT MODEL FOR UNSATURATED POROUS MEDIA

    SBC: Advanced Projects Research, Incorporated            Topic: N/A

    N/A

    SBIR Phase I 1992 Nuclear Regulatory Commission
  5. DEVELOPMENT OF TOOLS FOR SAFETY ANALYSIS OF CONTROL SOFTWARE IN ADVANCED REACTORS

    SBC: Advanced Systems Concepts            Topic: N/A

    N/A

    SBIR Phase I 1992 Nuclear Regulatory Commission
  6. Extending the Dynamic Flowgraph Methodology (DFM) to Model Human Performance and Team Effects

    SBC: ASCA, INC.            Topic: N/A

    N/A

    SBIR Phase I 1995 Nuclear Regulatory Commission
  7. ENHANCED REMOVAL OF RADIOACTIVE PARTICLES BY FLUOROCARBON SURFACTANT SOLUTIONS

    SBC: Entropic Systems, Inc.            Topic: N/A

    N/A

    SBIR Phase I 1992 Nuclear Regulatory Commission
  8. ENHANCEMENT TO STEAM GENERATOR TUBING EDDY CURRENT INSPECTION BY APPLICATION OF THERMALLY INDUCED STRESSES

    SBC: FOSTER-MILLER, INC.            Topic: N/A

    STEAM GENERATOR TUBES REPRESENT A UNIQUE PART OF THE REACTOR COOLANT SYSTEM (RCS). LEAKAGE FROM ANY OTHER PART OF THE RCS IS CAPTURED BY THE CONTAINMENT BUILDING, BUT STEAM GENERATOR TUBE LEAKAGE IS TRANSPORTED OUT OF THE CONTAINMENT BUILDING ALONG WITH THE STEAM, WHICH IS NORMALLY UNCONTAMINATED. STEAM GENERATOR TUBES, CONSEQUENTLY, DESERVE, AND RECEIVE SPECIAL CONSIDERATION. THE ASSURANCE OF STE ...

    SBIR Phase I 1992 Nuclear Regulatory Commission
  9. NONDESTRUCTIVE EXAMINATION TO DIRECTLY MEASURE STEAM GENERATOR TUBE U-BEND VIBRATORY RESPONSE

    SBC: FOSTER-MILLER, INC.            Topic: N/A

    ON FEBRUARY 9, 1991, AT THE MIHAMA UNIT 2 NUCLEAR POWER STATION, OPEARTED BY KANSAI ELECTRIC CORPORATION, A STEAM GENERATOR TUBE RUPTURED AND RELEASED APPROXIMATELY 9,000 GALLONS OF REACTOR COOLANT INTO THE SECONDARY SYSTEM. THE LEAKAGE CAUSED A RAPID DEPRESSURIZATION OF THE REACTOR COOLANT SYSTEM, WHICH RESULTED IN AN AUTOMATIC REACTOR TRIP AND ACTUATION OF THE HIGH PRESSURE SAFETY INJECTION SYST ...

    SBIR Phase I 1992 Nuclear Regulatory Commission
  10. 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
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