Download or read book Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission s Division of Nuclear Safety Research written by D. J. Claflin and published by . This book was released on 1979 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Quarterly Technical Progress Report on Water Reactor Safety Programs Sponsored by the Nuclear Regulatory Commission s Division of Reactor Safety Research April June 1981 Prepared for the U S Nuclear Regulatory Commission and Department of Energy Idaho Operations Office Under DOE Contract No DE AC07 76IDO1570 written by S. K. Edler and published by . This book was released on 1981 with total page 92 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Quarterly Technical Progress Report on Water Reactor Safety Programs Sponsored by the Nuclear Regulatory Commission s Division of Reactor Safety Research written by and published by . This book was released on 1980 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Quarterly Technical Progress Report on Water Reactor Safety Programs Sponsored by the Nuclear Regulatory Commission s Division of Reactor Safety Research January March 1978 Prepared for the U S Nuclear Regulatory Commission and Department of Energy Idaho Operations Office Under Contract No EY 76 C 07 1570 written by and published by . This book was released on 1978 with total page 61 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Quarterly Technical Progress Report on Water Reactor Safety Programs Sponsored by the Nuclear Regulatory Commission s Division of Reactor Safety Research April June 1980 written by L. J. Ybarrondo and published by . This book was released on 1980 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Quarterly Technical Progress Report on Water Reactor Safety Programs Sponsored by the Nuclear Regulatory Commission s Division of Reactor Safety Research October December 1980 written by and published by . This book was released on 1981 with total page 52 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Quarterly Technical Progress Report on Water Reactor Safety Programs Sponsored by the Nuclear Regulatory Commission s Division of Reactor Safety Research January March 1981 Prepared for the U S Nuclear Regulatory Commission and Department of Energy Idaho Operations Office Under DOE Contract No DE AC07 76IDO1570 written by J.A. Dearien and published by . This book was released on 1981 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Quarterly Technical Progress Report on Water Reactor Safety Programs Sponsored by the Nuclear Regulatory Commission s Division of Reactor Safety Research July September 1980 written by L. J. Ybarrondo and published by . This book was released on 1980 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Quarterly Technical Progress Report on Water Reactor Safety Programs Sponsored by the Nuclear Regulatory Commission s Division of Reactor Safety Research October December 1979 written by United States. Department of Energy. Idaho Operations Office and published by . This book was released on 1980 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Quarterly Technical Progress Report on Water Reactor Safety Programs Sponsored by the Nuclear Regulatory Commission s Division of Reactor Safety Research July September 1979 written by L. J. Ybarrondo and published by . This book was released on 1979 with total page 43 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Quarterly Technical Progress Report on Water Reactor Safety Programs Sponsored by the Nuclear Regulatory Commission s Division of Reactor Safety Research July September 1978 written by L. J. Ybarrondo and published by . This book was released on 1978 with total page 66 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Quarterly Technical Progress Report on Water Reactor Safety Programs Sponsored by the Nuclear Regulatory Commission s Division of Reactor Safety Research January March 1979 written by L. J. Ybarrondo and published by . This book was released on 1979 with total page 66 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Quarterly Technical Progress Report on Water Reactor Safety Programs Sponsored by the Nuclear Regulatory Commission s Division of Reactor Safety Research October December 1975 written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Light water reactor safety activities performed during October--December 1975 are reported. The blowdown heat transfer tests series of the Semiscale Mod-1 test program was completed. In the LOFT Program, preparations were made for nonnuclear testing. The Thermal Fuels Behavior Program completed a power-cooling-mismatch test and an irradiation effects test on PWR-type fuel rods. Model development and verification efforts of the Reactor Behavior Program included developing new analysis models for the RELAP4 computer code, subroutines for the FRAP-S and FRAP-T codes, and new models for predicting reactor fuel restructuring and zircaloy cladding behavior; an analysis of post-CHF fuel behavior was made using FRAP-T.

Download or read book Quarterly Technical Progress Report on Water Reactor Safety Programs Sponsored by the Nuclear Regulatory Commission s Division of Reactor Safety Research April June 1977 written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Results from the previously conducted Semiscale Mod-1 ECC injection test series were analyzed. Testing in the LOFT counterpart test series was essentially completed, and the steam generator tube rupture test series was begun. Two tests in the alternate ECC injection test series were conducted which included injection of emergency core coolant into the upper plenum through use of the low pressure injection system. The Loss-of-Fluid Test Program successfully completed nonnuclear Loss-of-Coolant Experiment L1-4. A nuclear test, GC 2-3, in the Power Burst Facility Reactor was performed to evaluate the power oscillation method of determining gap conductance and to determine the effects of initial gap size, fill gas composition, and fuel density on the thermal performance of a light water reactor fuel rod. Additional test results were obtained relative to the behavior of irradiated fuel rods during a fast power increase and during a high power film boiling transient. Fuel model development and verification activities continued for the steady state and transient Fuel Rod Analysis Program, FRAP-S and FRAP-T.A computer code known as RELAP4/MOD7 is being developed to provide best-estimate modeling for reflood during a postulated loss-of-coolant accident (LOCA). A prediction of the fourth test in the boiling water reactor (BWR) Blowdown/Emergency Core Cooling Program was completed and an uncertainty analysis was completed of experimental steady state stable film boiling data for water flowing vertically upward in round tubes. A new multinational cooperative program to study the behavior of entrained liquid in the upper plenum and cross flow in the core during the reflood phase of a pressurized water reactor LOCA was defined.

Download or read book Quarterly Technical Progress Report on Water Reactor Safety Programs Sponsored by the Nuclear Regulatory Commission s Division of Reactor Safety Research January March 1977 written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A test series to evaluate the effectiveness of different emergency core coolant injection arrangements was completed. A LOFT test series was initiated to investigate the effect of break nozzle geometry on break flow and system response during a 200 percent double-ended cold leg break test. Two analyses of results of LOFT nonnuclear experiments were made. The intact loop flow resistance on LOFT system responses during loss-of-coolant experiments was evaluated. The second in a series of five tests to evaluate the effects of fuel density, initial gap width, and fill gas composition on gap conductance was performed with four BWR-type rods tested simultaneously. A test was conducted to provide steady state, power ramp, and film boiling operation behavior data on the fuel rods constructed from irradiated and unirradiated cladding and to investigate the influence of simulated fission products on cladding integrity and performance. Cladding ballooning phenomena were also investigated. Results of preliminary postirradiation examinations of irradiation effects, power-cooling mismatch, and gap conductance tests performed previously are reported. A review of FLECHT and Semiscale forced feed and gravity feed reflood heat transfer experiments was performed. A study to predict and compare surface temperature response of Semiscale electrically heated rods with LOFT nuclear rods during a Semiscale blowdown was completed. SPERT and NSRR data were analyzed to evaluate fuel failure modes and the effect of energy deposition for cold-startup conditions.

Download or read book Quarterly Technical Progress Report on Water Reactor Safety Programs Sponsored by the Nuclear Regulatory Commission s Division of Reactor Safety Research January March 1976 written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Light water reactor sfaety research performed January through March 1976 is summarized. Results of the Semiscale Mod-1 blowdown heat transfer test series relating to those phenomena that influence core fluid and heat transfer effects are analyzed, and preliminary analyses of the recently completed reflood heat transfer test series are summarized for the forced and gravity feed reflood tests. The first nonnuclear LOCE in the LOFT program was successfully completed and preliminary results are presented. Preliminary results are given for the PCM 8-1 RF Test, the PCM-2A Test, and the Irradiation Effects Scoping Test 2 in the Thermal Fuel Behavior Program. Model development and verification efforts reported in the Reactor Behavior Program include checkout of RELAP4/MOD5 Update 1, development of a new hydrodynamic model for two-phase separated flows, development of the RACHET code to assess the assumptions in current fuel behavior codes of uniform stress and strain in the cladding, modifications of the containment code BEACON, analysis of results from the Halden Assembly IFA-429 helium sorption experiment, development of correlations for the thermal conductivity of UO/sub 2/ and (U, Pu)O/sub 2/, and evaluation of RALAP4 through comparison of calculated results with data from the GE Blowdown Heat Transfer and Semiscale experiments.

Download or read book Quarterly Technical Progress Report on Water Reactor Safety Programs Sponsored by the Nuclear Regulatory Commission s Division of Reactor Safety Research October December 1976 written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Light water reactor safety research performed October through December 1976 is discussed. An analysis to determine the effect of emergency core coolant (ECC) injection location and pump speed on system response characteristics was performed. An analysis to evaluate the capability of commonly used critical heat flux (CHF) correlations to calculate the time of the first CHF in the Semiscale core during a loss-of-coolant experiment (LOCE) was performed. A test program and study to determine the effect thermocouples mounted on the outside fuel rod surfaces would have on the departure from nucleate boiling (DNB) phenomena in the LOFT core during steady state operation were completed. A correlation for use in predicting DNB heat fluxes in the LOFT core was developed. Tests of an experimental transit time flowmeter were completed. A nuclear test was performed to obtain fuel rod behavior data from four PWR-type rods during film boiling operation representative of PWR conditions. Preliminary results from the postirradiation examination of Test IE-1 fuel rods are given. Results of Irradiation Effects Tests IE-2 and IE-3 are given. Gap Conductance Test GC 2-1 was performed to evaluate the effects of fuel density, initial gap width, and fill gas composition on the pellet-cladding gap conductance.