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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.

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. A COMPUTER CODE FOR FIRE PROTECTION AND RISK ANALYSIS OF NUCLEAR PLANTS.

    SBC: CFD Research Corporation            Topic: N/A

    THE PROPOSED RESEARCH IS TO ADVANCE THE STATE-OF-THE-ART OF DETERMINISTIC RISK ANALYSIS AND FIRE PROTECTION METHODOLOGY OF NUCLEAR POWER PLANTS. A COMPUTER CODE, BASED ON THE USE OF A FIELD (DISCRETIZATION) MODELING TECHNIQUE, WILL BE DEVELOPED THAT HAS SUFFICIENT FLEXIBILITY FOR ACCURATE/REALISTIC REPRESENTATIONS OF GEOMETRY, VENTILATION AND OTHER CONDITIONS PRESENT IN CABLE ROOMS AND CONTROL ROO ...

    SBIR Phase I 1987 Nuclear Regulatory Commission
  2. 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
  3. AGING PROCESSES IN NUCLEAR REACTORS

    SBC: Pdi Technology Inc            Topic: N/A

    AS NUCLEAR PLANTS GROW OLDER, ENVIRONMENTAL CONDITIONS MAY AFFECT THE PERFORMANCE OF PLANT CONCRETE AND STEEL STRUCTURES. WE PROPOSE TO DEVELOP A STRATEGY WHICH CAN BE APPLIED TO CONCRETE STRUCTURES. IT WILL BE DIRECTED TOWARDSTHE DEVELOPMENT OF METHODS TO ANALYZE AND UNDERSTAND AGING EFFECTS, INCLUDING THE COMBINED EFFECTS OF TIME, TEMPERATURE, RADIATION, HUMIDITY, STRESS, CHEMICAL ENVIRONMENT AN ...

    SBIR Phase I 1987 Nuclear Regulatory Commission
  4. ANALYSIS OF STATE-OF-THE-ART METHODS FOR CONTAINMENT INTEGRATED LEAK RATE TESTING

    SBC: Sentry Equipment Corp.            Topic: N/A

    N/A

    SBIR Phase I 1987 Nuclear Regulatory Commission
  5. 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
  6. AUTOMATIC CREATION AND RENODALIZATION OF TRAC-BWR INPUT DECKS

    SBC: Expert-ease Systems            Topic: N/A

    THE OBJECTIVE OF THE PROPOSED RESEARCH IS TO BUILD A USER-FRIENDLY, PERSONAL COMPUTER BASED WORKSTATION FOR PERFORMING TRAC-BWR ANALYSIS. THE SOFTWARE WILL ALLOW A USER TO READ-IN DATA FROM EXISTING TRAC-BWR INPUT DECKS (ASCII), DRAW NODALIZATION DIAGRAM, MODIFY INPUT, AUTOMATICALLY RENODALIZE THE VESSEL, CHAN AND PIPE COMPONENTS, GENERATE INPUT DECK, SUBMIT JOB, BRING BACK PLOTDATA, DISPLAY RESUL ...

    SBIR Phase I 1987 Nuclear Regulatory Commission
  7. 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
  8. 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
  9. DEGRATION OF NUCLEAR PLANT TEMPERATURE SENSORS

    SBC: ANALYSIS AND MEASUREMENT SERVICES CORPORATION            Topic: N/A

    SAFETY SYSTEM TEMPERATURE SENSORS IN NUCLEAR POWER PLANTS ARE SUBJECT TO PERFORMANCE DEGRATION BECAISE PF AGING EFFECTS. A PROGRAM OF LABORATORY TESTING AND IN-SITU TESTINGIS NEEDED TO ENSURE THAT AGING DOES NOT LEAD TO REDUCED SAFETY AND AVAILABILITY. MUCH OF THE TECHNOLOGY NEEDED FOR THIS PROGRAM NOW EXISTS AS ISOLATED METHODS AND PROCEDURES. THESE WILL BE USED IN THIS PROJECT TO PERFORM AN AGIN ...

    SBIR Phase II 1987 Nuclear Regulatory Commission
  10. 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
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