Read Books Online and Download eBooks, EPub, PDF, Mobi, Kindle, Text Full Free.
Experimental Studies Of Transient Effects In Fast Reactor Fuels Series I Uosub 2 Irradiations
Download Experimental Studies Of Transient Effects In Fast Reactor Fuels Series I Uosub 2 Irradiations full books in PDF, epub, and Kindle. Read online Experimental Studies Of Transient Effects In Fast Reactor Fuels Series I Uosub 2 Irradiations ebook anywhere anytime directly on your device. Fast Download speed and no annoying ads. We cannot guarantee that every ebooks is available!
Book Synopsis Experimental Studies of Transient Effects in Fast Reactor Fuels by : J. H. Field
Download or read book Experimental Studies of Transient Effects in Fast Reactor Fuels written by J. H. Field and published by . This book was released on 1962 with total page 84 pages. Available in PDF, EPUB and Kindle. Book excerpt: An experimental program to evaluate the performance of FCR and EFCR fuel during transient operation is outlined, and the initial series of tests are described in some detail. Test results from five experiments in the TREAT reactor, using 1-in. OD SS-clad UO2 fuel specimens, are compared with regard to fuel temperatures, mechanical integrity, and post-irradiation appearance. Incipient fuel pin failure limits for transients are identified with maximum fuel temperatures in the range of 7000 deg F. Multiple transient damage to the cladding is likely for transients above the melting point of the fuel.
Book Synopsis EXPERIMENTAL STUDIES OF TRANSIENT EFFECTS IN FAST REACTOR FUELS. SERIES II. MIXED OXIDE (PuO2-UO2) IRRADIATIONS. by :
Download or read book EXPERIMENTAL STUDIES OF TRANSIENT EFFECTS IN FAST REACTOR FUELS. SERIES II. MIXED OXIDE (PuO2-UO2) IRRADIATIONS. written by and published by . This book was released on 1965 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis EXPERIMENTAL STUDIES OF TRANSIENT EFFECTS IN FAST REACTOR FUELS. SERIES III. PRE-IRRADIATED MIXED OXIDE (PuO2--UO2) IRRADIATIONS. FINAL REPORT. TRANSIENT IRRADIATIONS. by :
Download or read book EXPERIMENTAL STUDIES OF TRANSIENT EFFECTS IN FAST REACTOR FUELS. SERIES III. PRE-IRRADIATED MIXED OXIDE (PuO2--UO2) IRRADIATIONS. FINAL REPORT. TRANSIENT IRRADIATIONS. written by and published by . This book was released on 1967 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis EXPERIMENTAL STUDIES OF TRANSIENT EFFECTS IN FAST REACTOR FUELS. SERIES I. UO$sub 2$ IRRADIATIONS. by :
Download or read book EXPERIMENTAL STUDIES OF TRANSIENT EFFECTS IN FAST REACTOR FUELS. SERIES I. UO$sub 2$ IRRADIATIONS. written by and published by . This book was released on 1962 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: An experimental program to evaluate the performance of FCR and EFCR fuel during transient operation is outlined, and the initial series of tests are described in some detail. Test results from five experiments in the TREAT reactor, using 1-in. OD SS-clad UO/sub 2/ fuel specimens, are compared with regard to fuel temperatures, mechanical integrity, and post-irradiation appearance. Incipient fuel pin failure limits for transients are identified with maximum fuel temperatures in the range of 7000 deg F. Multiple transient damage to the cladding is likely for transients above the melting point of the fuel. (auth).
Book Synopsis EXPERIMENTAL STUDIES OF TRANSIENT EFFECTS IN FAST REACTOR FUELS. SERIES I. UO2 IRRADIATIONS. by :
Download or read book EXPERIMENTAL STUDIES OF TRANSIENT EFFECTS IN FAST REACTOR FUELS. SERIES I. UO2 IRRADIATIONS. written by and published by . This book was released on 1962 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: An experimental program to evaluate the performance of FCR and EFCR fuel during transient operation is outlined, and the initial series of tests are described in some detail. Test results from five experiments in the TREAT reactor, using 1-in. OD SS-clad UO2 fuel specimens, are compared with regard to fuel temperatures, mechanical integrity, and post-irradiation appearance. Incipient fuel pin failure limits for transients are identified with maximum fuel temperatures in the range of 7000 deg F. Multiple transient damage to the cladding is likely for transients above the melting point of the fuel. (auth).
Book Synopsis EXPERIMENTAL STUDIES OF TRANSIENT EFFECTS IN FAST REACTOR FUELS. SERIES III. PRE-IRRADIATED MIXED OXIDE (PuO2-UO2) IRRADIATIONS. INTERIM REPORT. STEADY-STATE IRRADIATIONS. by :
Download or read book EXPERIMENTAL STUDIES OF TRANSIENT EFFECTS IN FAST REACTOR FUELS. SERIES III. PRE-IRRADIATED MIXED OXIDE (PuO2-UO2) IRRADIATIONS. INTERIM REPORT. STEADY-STATE IRRADIATIONS. written by and published by . This book was released on 1965 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Analytical Studies of Transient Effect in Fast Reactor Fuels by : R. B. Osborn
Download or read book Analytical Studies of Transient Effect in Fast Reactor Fuels written by R. B. Osborn and published by . This book was released on 1962 with total page 51 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis STUDIES OF FAST REACTOR FUEL ELEMENT BEHAVIOR UNDER TRANSIENT HEATING TO FAILURE. II. INPILE EXPERIMENTS ON UO2 SAMPLES IN THE ABSENCE OF COOLANT. by :
Download or read book STUDIES OF FAST REACTOR FUEL ELEMENT BEHAVIOR UNDER TRANSIENT HEATING TO FAILURE. II. INPILE EXPERIMENTS ON UO2 SAMPLES IN THE ABSENCE OF COOLANT. written by and published by . This book was released on 1965 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis STUDIES OF FAST REACTOR FUEL ELEMENT BEHAVIOR UNDER TRANSIENT HEATING TO FAILURE. III. IN-PILE EXPERIMENTS ON IRRADIATED UO$sub 2$ FUEL PINS IN THE ABSENCE OF COOLANT. by :
Download or read book STUDIES OF FAST REACTOR FUEL ELEMENT BEHAVIOR UNDER TRANSIENT HEATING TO FAILURE. III. IN-PILE EXPERIMENTS ON IRRADIATED UO$sub 2$ FUEL PINS IN THE ABSENCE OF COOLANT. written by and published by . This book was released on 1969 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Irradiation Experimentation in Fast Reactors by :
Download or read book Irradiation Experimentation in Fast Reactors written by and published by . This book was released on 1973 with total page 522 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Irradiation Behavior of Metallic Fast Reactor Fuels by :
Download or read book Irradiation Behavior of Metallic Fast Reactor Fuels written by and published by . This book was released on 1991 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt: Metallic fuels were the first fuels chosen for liquid metal cooled fast reactors (LMR's). In the late 1960's world-wide interest turned toward ceramic LMR fuels before the full potential of metallic fuel was realized. However, during the 1970's the performance limitations of metallic fuel were resolved in order to achieve a high plant factor at the Argonne National Laboratory's Experimental Breeder Reactor II. The 1980's spawned renewed interest in metallic fuel when the Integral Fast Reactor (IFR) concept emerged at Argonne National Laboratory. A fuel performance demonstration program was put into place to obtain the data needed for the eventual licensing of metallic fuel. This paper will summarize the results of the irradiation program carried out since 1985.
Book Synopsis Studies of Fast Reactor Fuel Element Behavior Under Transient Heating to Failure by : R. R. Stewart
Download or read book Studies of Fast Reactor Fuel Element Behavior Under Transient Heating to Failure written by R. R. Stewart and published by . This book was released on 1969 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Investigation of Fast Reactor Fuel Pin Start-up Behaviour in the DUELL-II Series of Irradiation Experiments by : D Freud
Download or read book Investigation of Fast Reactor Fuel Pin Start-up Behaviour in the DUELL-II Series of Irradiation Experiments written by D Freud and published by . This book was released on 1988 with total page 62 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fuel Damage During Off-normal Transients in Metal-fueled Fast Reactors by :
Download or read book Fuel Damage During Off-normal Transients in Metal-fueled Fast Reactors written by and published by . This book was released on 1990 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: Fuel damage during off-normal transients is a key issue in the safety of fast reactors because the fuel pin cladding provides the primary barrier to the release of radioactive materials. Part of the Safety Task of the Integral Fast Reactor Program is to provide assessments of the damage and margins to failure for metallic fuels over the wide range of transients that must be considered in safety analyses. This paper reviews the current status of the analytical and experimental programs that are providing the bases for these assessments. 13 refs., 2 figs.
Book Synopsis Transient Feedback from Fuel Motion in Metal IFR (Integral Fast Reactor) Fuel by :
Download or read book Transient Feedback from Fuel Motion in Metal IFR (Integral Fast Reactor) Fuel written by and published by . This book was released on 1990 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: Results from hodoscope data analyses are presented for TREAT transient-overpower tests M5 through M7 with emphasis on transient feedback mechanisms, including prefailure expansion at the tops of the fuel pins, subsequent dispersive axial fuel motion, and losses in relative worth of the fuel pins during the tests. Tests M5 and M6 were the first TOP tests of margin to cladding branch and prefailure elongation of D9-clad ternary (U-Pu-Zr) IFR-type fuel. Test M7 extended these results to high-burnup fuel and also initiated transient testing of HT9-clad binary (U-Zr) FFTF-driver fuel. Results show significant prefailure negative reactivity feedback and strongly negative feedback from fuel driven to failure. 4 refs., 6 figs.
Book Synopsis Reliability of Fast Reactor Mixed-oxide Fuel During Operational Transients by :
Download or read book Reliability of Fast Reactor Mixed-oxide Fuel During Operational Transients written by and published by . This book was released on 1991 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt: Results are presented from the cooperative DOE and PNC Phase 1 and 2 operational transient testing programs conducted in the EBR-2 reactor. The program includes second (D9 and PNC 316 cladding) and third (FSM, AST and ODS cladding) generation mixed-oxide fuel pins. The irradiation tests include duty cycle operation and extended overpower tests. the results demonstrate the capability of second generation fuel pins to survive a wide range of duty cycle and extended overpower events. 15 refs., 9 figs., 4 tabs.
Book Synopsis Modeling the Behavior of Metallic Fast Reactor Fuels During Extended Transients by :
Download or read book Modeling the Behavior of Metallic Fast Reactor Fuels During Extended Transients written by and published by . This book was released on 1992 with total page 21 pages. Available in PDF, EPUB and Kindle. Book excerpt: Passive safety features in the metal-fueled Integral Fast Reactor (IFR) make it possible to avoid core damage for extended time periods even when automatic scram systems fail to operate or heat removal systems are severely degraded. The time scale for these transients are intermediate between those that have traditionally been analyzed in fast reactor safety assessments and those of normal operation. Consequently, it has been necessary to validate models and computer codes (FPIN2 and LIFE-METAL) for application to this time regime. Results from out-of-reactor Whole Pin Furnace tests are being used for this purpose. Pretest predictions for tests FM-1 through FM-6 have been performed and calculations have been compared with the experimental measurements.
