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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. 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
  2. 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
  3. 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
  4. 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
  5. 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
  6. 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
  7. 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
  8. METHODS TO UNDERSTAND AND ANALYZE AGING EFFECTS

    SBC: Sea Consultants            Topic: N/A

    N/A

    SBIR Phase I 1985 Nuclear Regulatory Commission
  9. PROBABILITY OF FLOODS WITH VERY LONG RETURN PERIODS

    SBC: Linsley Kraeger Associates Ltd            Topic: N/A

    THIS PROPOSAL IS DIRECTED TO THE DEVELOPMENT OF A PROCEDURE FOR GENERATING LONG STREAMFLOW SEQUENCES. IT IS PROPOSED TO FIRST DEVELOP A LONG SEQUENCE OF HOURLY RAINFALL BY STOCHASTIC METHODS AND TO TRANSFORM THIS RAINFALL SEQUENCE INTO STREAMFLOW WITH A DETERMINISTIC HYDROLOGIC MODEL. PHASE I WILL FOCUS ON THE A STOCHASTIC RAINFALL MODEL CAPABLE OF DEVELOPING RAINFALL SEQUENCES AT MULTIPLE SITES. ...

    SBIR Phase II 1985 Nuclear Regulatory Commission
  10. "EXTENDING A HCLPF-BASED SEISMIC MARGIN REVIEW TO ANALYZE PLANT DAMAGE STATES AND THE ROLE OF HUMAN FACTORS AND NON-SEISMIC FAILURES"

    SBC: Future Resources Associate Inc            Topic: N/A

    TECHNIQUES HAVE RECENTLY BEEN DEVELOPED TO ANALYZE THE 'SEISMIC MARGIN' OF A NUCLEAR POWER PLANT USING THE HCLPF CONCEPT (HIGH CONFIDENCE OF A LOW PROBABILITY OF FAILURE). STARTING WITH AN EARTHQUAKE LEVEL SHOSEN FOR MARGIN REVIEW, THE TECHNIQUE DETERMINES WHETHER THE PLANT CAN OR CANNOT 'WITHSTAND THE REVIEW-EARTHQUAKE WITHOUT CORE DAMAGE. HERE 'WITHSTAND' MEANS 'WITHSTAND WITH A HIGH CONFIDENCE ...

    SBIR Phase II 1987 Nuclear Regulatory Commission
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