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Award Data

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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. ENHANCED SIMULATOR TRAINING PROGRAM FOR OPERATORS AT MULTI-UNIT PLANTS.

    SBC: Corpe Corp.            Topic: N/A

    AT MULTI-UNIT NUCLEAR GENRATING STATIONS, CONTROL ROOM OPERATORS ARE GENERALLY LICENSED TO OPERATE ALL SIMILAR UNITS. SIMULATOR TRAINING CONDUCTED AT THE LICENSEE TRAINING FACILITY OCCURS ON ONE SIMULATOR WHICH MAY NOT EXACTLY MIMIC ANY UNIT. INADEQUATE TRAINING ON UNIT-TO-UNIT AND UNIT-TO-SIMULATOR DIFFERENCES, IN CONJUNCTION WITH LIMITED PER-PERSON SIMULATOR TRAINING HOURS, CAN RESULT IN INCREAS ...

    SBIR Phase I 1994 Nuclear Regulatory Commission
  2. ON-LINE PLANT ANALYZER UTILIZATION IN CONTROL ROOM FOR SURVEILLANCE OF PLANT SAFETY

    SBC: Dynatrek Inc.            Topic: N/A

    THE PRINCIPAL SCOPE OF THE PROPOSED RESEARCH IS TO DEVELOP SOFTWARE FOR A BC-CONTROLLER WHOSE PURPOSE IS TO SUPPLY AND CONSTANTLY UPDATE THE BOUNDARY CONDITIONS (BC) TO AN ON-LINE PLANT ANALYZER, ENABLING IT TO FAITHFULLY TRACK A NUMBER OF THE CONTINUOUSLY MEASURED PLANT PARAMETERS. THE BC-CONTROLLER SAMPLES PLANT MEASUREMENTS FROM THE PLANT COMPUTER MEMORY. THE PLANT ANALYZER, IN TURN, PROVIDES D ...

    SBIR Phase II 1985 Nuclear Regulatory Commission
  3. ON-LINE PLANT ANALYZER UTILIZATION IN CONTROL ROOM FOR SURVEILLANCE OF PLANT SAFETY

    SBC: Dynatrek Inc.            Topic: N/A

    N/A

    SBIR Phase I 1984 Nuclear Regulatory Commission
  4. HIGH SENSITIVITY URANIUM BIOASSAY

    SBC: Eastern Analytical Inc.            Topic: N/A

    DETERMINATION OF URANIUM IN THE URINE OF WORKERS IS REQUIRED BY THE NRC AT NUCLEAR FACILITIES. EXTREMELY LOW CONCENTRATIONS OF URANIUM, ESPECIALLY IN SMALL SAMPLES, ARE DIFFICULT TO MEASURE USING EXISTING TECHNOLOGY. FUTURE NRC PLANS TO CHARACTERIZE BIOAVAILABLE URANIUM FRACTIONS COMPRISING THE URANIUM BODY BURDEN WILL REQUIRE EVEN HIGHER SENSITIVITIES. HIGH SENSITIVITY TECHNOLOGY DEVELOPED FOR UR ...

    SBIR Phase I 1992 Nuclear Regulatory Commission
  5. 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
  6. ROBUST, ACCURATE, NON-CONTACTING VIBRATION MEASUREMENT SYSTEM

    SBC: EPOCH ENGINEERING, INC.            Topic: N/A

    WHEN ROTATING MACHINERY DETERIORATES, VIBRTION PATTERSN CHANGE. WHEN BEARING FREQUENCIES APPEAR, THEN INCREASE IN AMPLITUDE, BEARING FAILURE LOOMS. THE SAME WITH VALVES; WHEN THEY LEAK, THEY VIBRATE. AS LEAKAGE INCREASES, THE VIBRATION PATTERN CHANGES. THERE ARE MANY OTHERS. THE KEY IS KNOWING WHERE AND HOW DEEPLY TO LOOK. THE KEY IN OLDER REACTOR PLANTS IS TO UNOBTRUSIVELY, ECONOMICALLY BACKFIT S ...

    SBIR Phase I 1994 Nuclear Regulatory Commission
  7. DEVELOPMENT OF IMPROVED TECHNIQUES FOR DYNAMIC PRA

    SBC: Frh, Inc.            Topic: N/A

    CHANGES IN PLANT STATUS, EITHER BEFORE OR DURING AN ACCIDENT SEQUENC CAN CONSIDERABLY AFFECT ITS OUTCOME; BOTH THE ACTURAL OUTCOME AND THAT PREDICTED BY PROBABILISTIC RISK ASSESSMENT. IN ORDER TO ACCURATELY REPRESENT THE POSSIBLE ACCIDENTS AND THEIR PROBABILITIES, THE PRA MODEL MUST CONSIDER THE DYNAMIC CHARACTER OF THE PLANT, IT'S SYSTEMS AND OPERATORS. A LIVING, DYNAMIC PRA IS ONE IN WHICH ALL T ...

    SBIR Phase I 1994 Nuclear Regulatory Commission
  8. USE OF CERAMIC FUEL CLADDING TO REDUCE THE SEVERITY OF LMR ACCIDENTS

    SBC: Gamma Engineering Corporation            Topic: N/A

    THIS PROJECT INVESTIGATES THE FEASIBILITY OF USING CERAMIC CLADDING MATERIALS TO REPLACE THE METALLIC CLADDING MATERIALS NOW USED WITH WATER REACTOR FUEL. SHOULD FEASIBILITY BE DETERMINED, AND EVENTUALLY COMMERCIALIZED, THE ABILITY OF WATER REACTORS TO WITHSTAND SEVERE ACCIDENTS WOULD BE ENHANCED. WITH TODAYS METAL CLAD FUEL, A RELATIVELY SHORT TIME PERIOD IS AVAILABLE AFTER A LOSS OF COOLANT ACCI ...

    SBIR Phase I 1989 Nuclear Regulatory Commission
  9. PERFORM AND REPORT EXPERIMENTS TO DEMONSTRATE THE FEASIBILITY OF THE CONCEPT.

    SBC: Leak Detection Services Inc            Topic: N/A

    PERFORM AND REPORT EXPERIMENTS TO DEMONSTRATE THE FEASIBILITY OF THE CONCEPT.

    SBIR Phase I 1985 Nuclear Regulatory Commission
  10. 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
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