You are here

Award Data

For best search results, use the search terms first and then apply the filters
Reset

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. BUNDLES UNDER LOW REFLOOD RATES AND BOIL OFF CONDITIONS

    SBC: Mohr And Associates            Topic: N/A

    THIS PROGRAM DEALS WITH USING THE DIGITIZED VIDEO TDR LIQUIDLEVEL DATA PREPARED UNDER CONTRACT (NRC-04-84-146) OF THE MEMT-4 TEST FROM THE LOCA SIMULATION IN NRU PROGRAM. THESE NEW DATA AND TECHNIQUES WILL BE APPLIED TO ESTIMATE THE VOIDFRACTION, LIQUID LEVEL, AND LOCAL HEAT TRANFER CONDITIONS FOR THE OTHER NRU TESTS WHERE ONLY SELF POWERED NEUTRON DETECTORS (SPND'S) AND THERMOCOUPLE DATA ARE AVAI ...

    SBIR Phase I 1985 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. EXTENDED FATIGUE LIFE EVALUATION METHODS FOR AGED LWR COMPONENTS

    SBC: O'donnell Consulting Engineers            Topic: N/A

    N/A

    SBIR Phase I 1985 Nuclear Regulatory Commission
  6. FACILITATE DEVELOPMENT AND EVALUATION OF FAULT TREES

    SBC: Expert-ease Systems            Topic: N/A

    WORKSTATION AND EXPERT SYSTEM TECHNOLOGIES HAVE A POTENTIAL OF SUBSTANTIALLY FACILITATING THE DEVELOPMENT AND EVALUATIONOF FAULT TREES. INTRODUCING A WORKSTATION PHILOSOPHY WITH AN INTERACTIVE SET OF INTEGRATED SOFTWARE TOOLS ON A LOCAL COMPUTER WILL PROMOTE IMPROVED CONTINUITY IN THE THOUGHT PROCESS DURING A FAULT TREE DEVELOPMENT. THE EXPERT SYSTEM TECHNOLOGY WILL SIMPLIFY THE WAY FAULT TREES AR ...

    SBIR Phase I 1985 Nuclear Regulatory Commission
  7. 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
  8. GENERALIZED MODELING OF CONDENSATION FOR REACTOR APPLICATION

    SBC: CREARE LLC            Topic: N/A

    N/A

    SBIR Phase I 1985 Nuclear Regulatory Commission
  9. HYDROGEN GENERATION AND BLANKETING ASSESSMENT FOR SEVERE ACCIDENTS

    SBC: ENGINEERING SCIENCE ANALYSIS CORP            Topic: N/A

    N/A

    SBIR Phase I 1985 Nuclear Regulatory Commission
  10. IN-REACTOR MEASUREMENTS INVOLVING ELECTROCHEMICAL POTENTIAL A NUMBER OF BOILING WATER REACTORS (BWRS) SUGGEST THAT THE WATER CHEMISTRY OF THE PRIMARY COOLANT OF EACH BWR MAY BE UNIQUE WITH RESPECT TO ITS ABILITY TO FACILITATE IGSCC AND/ OR MAY CHANGE

    SBC: Michael Fox            Topic: N/A

    IN-REACTOR MEASUREMENTS INVOLVING ELECTROCHEMICAL POTENTIAL A NUMBER OF BOILING WATER REACTORS (BWRS) SUGGEST THAT THE WATER CHEMISTRY OF THE PRIMARY COOLANT OF EACH BWR MAY BE UNIQUE WITH RESPECT TO ITS ABILITY TO FACILITATE IGSCC AND/ OR MAY CHANGE WITH REACTOR OPERATING TIME OR AGE. THE WORK PROPOSED IS TO GATHER, REVIEW, ORGANIZE, COMPILE, C COMPUTERIZE, AND ANALYZE IN-REACTOR DATA PERTAINING ...

    SBIR Phase I 1985 Nuclear Regulatory Commission
US Flag An Official Website of the United States Government