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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.

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. 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
  2. BWR RECIRCULATION INLET SAFE ENDS-A THREAT TO PLANT LIFE ANDSAFETY

    SBC: Aptech Engineering Services            Topic: N/A

    AN ON-GOING THREAT TO THE RESIDUAL LIFETIME AND SAFETY OF BOILING WATER REACTORS (BWRS) IS INTERGRANULAR STRESS CORROSION CRACKING (IGSCC). A COMPONENT OF SPECIAL CONCERN IN THE RECIRCULATION INLET NOZZLE SAFE END (RINSE). FOR EXAMPLE, WITHIN THE LAST 2 YEARS 30 OUT OF 30 RINSES ARE KNOWN TO BE CRACKED AT A 3-UNIT BWR SITE AND IT IS BELIEVED THAT 20 OUT OF 20 RINSES ARE CRACKED AT A 2-UNIT BWR SIT ...

    SBIR Phase I 1989 Nuclear Regulatory Commission
  3. 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
  4. 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
  5. DEVELOPMENT OF A REAL TIME LONG RANGE RADIOACTIVE PLUME TRANSPORT SIMULATION MODEL

    SBC: PHYSICAL RESEARCH, INC.            Topic: N/A

    THE FEASIBILITY OF DEVELOPMENT OF A NEW LONG RANGE RADIOACTIVE PLUME TRANSPORT CODE IS PROPOSED. NEW APPROACHES TO ESTIMATE THE RADIOACTIVE DECAY, WET AND DRY DEPOSITION, PARTICULATE COAGULATION, AND ATMOSPHERIC PARAMETERS WILL BE EXPLORED AND A SIMPLE, IDEALIZED EVALUATION OF THESE ALGORITHMS WILL BE MADE IN PHASE I OF THE PROPOSED EFFORT. BASED ON THESE STUDIES A) AN APPROPRIATE NEAR SOURCE RISE ...

    SBIR Phase I 1989 Nuclear Regulatory Commission
  6. DEVELOPMLENT OF A LAUNDRY MONITOR FOR DETECTION OF HOT PARTICLE CONTAMINATION

    SBC: Shonka Research Associates            Topic: N/A

    N/A

    SBIR Phase I 1989 Nuclear Regulatory Commission
  7. DEV OF A LARGE CROSS SECTIONAL AREA SELF-POWERED DETECTOR

    SBC: K E M P CORP            Topic: N/A

    A SELF-POWERED RADIATION DETECTOR THAT CAN BE USED TO DETECTTHE SOURCE POSITION IN INDUSTRIAL RADIOGRAPHIC EQUIPMENT IS NEEDED. SELF-POWERED DETECTORS HAVE TRADITIONALLY BEEN USEDINFLUX MAPPING SYSTEMS IN NUCLEAR REACTORS BECAUSE OF THEIR SIZE, RUGGEDNESS AND SIMPLICITY. THIS DETECTOR CONCEP PROVIDES THE UNIQUE OPPORTUNITY FOR THE DEVELOPMENT OF LARGECROSS SECTIONAL AREA DETECTORS THATCAN BE USED ...

    SBIR Phase II 1989 Nuclear Regulatory Commission
  8. EFFECT OF AGING ON RESPONSE TIME OF NUCLEAR PLANT PRESSURE SENSORS

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

    PERIODIC RESPONSE TIME TESTING HAS BEEN PERFORMED FOR THE PAST TWELVE YEARS ON THE SAFETY SYSTEM PRESSURE SENSORS IN MANY NUCLEAR POWER PLANTS. HOWEVER, THE RESULTS OF THESE TESTS ARE NOT RELIABLE FOR ASSESSMENT OF AGING EFFECTS. THEIS BECAUSE INADEQUATE METHODS AND PROCEDURES HAVE BEEN USED IN PERFORMING THE MAJORITY OF THE TESTS. THIS PROPOSAL OFFFERS AN EXPERIMENTAL RESEARCH PROJECT TO PROVIDE ...

    SBIR Phase II 1989 Nuclear Regulatory Commission
  9. 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
  10. IMPROVED MODEL FOR PREDICTING J-R CURVES FROM CHARPY DATA

    SBC: Modeling & Computing Services            Topic: N/A

    IT IS NECESSARY TO ESTIMATE J-R OR JI DATA FOR AGING AND RE-SIDUAL LIFE STUDIES, USING DATA FROM SURVEILLANCE CAPSULE SPECIMENS THAT REFLECT THE CURRENT STATE OF THE PRESSURE VESSEL STEEL. AN IMPROVED MODEL IS NEEDED THAT WILL PREDICT J J-R DATA FROM CHARPY DATA, TENSILE PROPERTIES, MATERIAL COM-POSITION AND OTHER MEASURABLE PROPERTIES. SUCH A MODEL WILLBE DEVELOPED UNDER THIS PROJECT, USING INNOV ...

    SBIR Phase II 1989 Nuclear Regulatory Commission
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