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450/sup 0/F step transient thermal analysis of the LOFT pressurizer surge and spray line piping

Description: The LOFT pressurizer spray and surge line piping was analyzed for a 450/sup 0/F step change in fluid temperature. This transient was chosen to conservatively represent several pressurizer operating transients that had not previously been analyzed. These include temperature transients resulting from a 300/sup 0/F ..delta..T between pressurizer temperature and cold leg temperature, injection of a cooled (70/sup 0/F) slug of stagnant fluid into the hot (540/sup 0/F) spray line piping, and inflow o… more
Date: July 7, 1977
Creator: Tolan, B.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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2200/sup 0/C fuel centerline thermocouples for the LOFT program

Description: The technology as well as commercial suppliers have been developed for high temperature thermocouples for the Loss-of-Fluid-Test (LOFT) program. Two types of thermocouples were developed and tested. Model B units contained a 1/16-inch OD 24-inch long Mo/Re sheath probe and were capable of temperature measurement to 1550/sup 0/C. Model A units contained a 1/16-inch OD 41-inch long W/Re-augmented sheath probe and were capable of temperature measurement to 2200/sup 0/C.
Date: July 1, 1979
Creator: Cannon, C. P. & Lunghofer, J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Acoustic-emission monitoring of LOFT fuel-cladding-burst tests

Description: Experiments at the Loss-of-Fluid Test Facility (LOFT), beginning with experiment L6-8 (Anticipated Transient Experiment), will use a core equipped with several pressurized fuel rods. Because some of the tests may produce temperature and pressure conditions which could conceivably burst a number of rods, a nondestructive method for burst detection is needed. Acoustic emission monitoring of a number of tests of small zircaloy tubing samples, each with internal gas volume similar to that of an act… more
Date: February 1, 1982
Creator: Reinhardt, W. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Allowable outage analysis for the LOFT CIS and reflood assist bypass valves

Description: To determine the outage time allowable for a typical 1 of 2 redundant valve configuration, a Markov model was created to analyze the various operating states for the valves. Since no performance criteria have been specified, an availability model was constructed with regard to the valve outage.
Date: June 1, 1977
Creator: Trainer, J.E. & Matthews, S.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of a transient load measuring system

Description: An analysis of the performance of a load measuring system is presented. The load system was designed to measure the weight of a pressure vessel containing high pressure and temperature water. The uncertainty and frequency response of the system are quantified for both steady state and dynamic conditions as is the repeatability of the test rig. Computation of the mass flow exiting the system during explosive decompression of the system is also presented.
Date: January 1, 1980
Creator: Good, R. R. & Meachum, T. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Analysis of LOFT containment nozzles 11A, 11B, 11D, 12A, 13B, 13C, and 13D by Bijlaard method

Description: The purpose of this analysis was the calculation of stresses in the LOFT Containment Vessel at the point of nozzle penetration produced by loads on the nozzles and to show that those stresses are within the 1965 ASME Boiler and Pressure Vessel Code allowables. The stress determination was done by the method developed by P. P. Bijlaard on the worst load case for each diameter nozzle. The operating basis earthquake (OBE) at nozzle 11D produced the most severe load case. All load cases resulted in… more
Date: July 24, 1978
Creator: McFadden, D.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analysis of LOFT pressurizer spray and surge nozzles to include a 450/sup 0/F step transient

Description: This report presents the analysis of the LOFT pressurizer spray and surge nozzles to include a 450/sup 0/F step thermal transient. Previous analysis performed under subcontract by Basic Technology Incorporated was utilized where applicable. The SAASIII finite element computer program was used to determine stress distributions in the nozzles due to the step transient. Computer results were then incorporated in the necessary additional calculations to ascertain that stress limitations were not ex… more
Date: January 18, 1978
Creator: Nitzel, M.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analysis of LOFT steam generator main feed piping loop seal modification

Description: The stress analysis is presented for the proposed loop seal modification to the LOFT Steam Generator Main Feed Piping. THE SAP IV finite element computer program was used to analyze normal, upset, emergency, and faulted conditions. Results of the analysis indicate that the modified main feed piping system will satisfy all structural adequacy criteria specified in Subarticle NC-3650 of the ASME Boiler and Pressure Vessel Code. Results also show that the isolation snubber configuration, specified… more
Date: February 14, 1978
Creator: Nitzel, M.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analysis of LOFT Tests L2-2, L2-3 and L3-0

Description: This paper describes LOFT Tests L2-2, L2-3, and L3-0 and presents conclusions reached from analysis of these tests. The LOFT L2 series of tests, called the power ascension series, originally consisted of six tests. The first four tests, L2-1 through L2-4, were identical except for step-wise increases in core power for each test. Comparison of these tests, and the nonnuclear Test L1-5, was planned to evaluate the effect of core power on system and ECC behavior during large cold leg break LOCA's.… more
Date: January 1, 1979
Creator: Leach, L.P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Analysis of proposed gamma-ray detection system for the monitoring of core water inventory in a pressurized water reactor

Description: An initial study has been performed of the feasibility of employing an axial array of gamma detectors located outside the pressure vessel to monitor the coolant in a PWR. A one-dimensional transport analysis model is developed for the LOFT research reactor and for a mock-PWR geometry. The gamma detector response to coolant voiding in the core and downcomer has been determined for both geometries. The effects of various conditions (for example, time after shutdown, materials in the transport pat… more
Date: December 1, 1987
Creator: Markoff, Diane Melanie
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of the LOFT Modular Drag Disc Turbine Transducer (MDTT) spring for compressive buckling

Description: The LOFT Modular Drag Disc Turbine Transducer (MDTT) springs (for range 2, rhoV/sup 2/ = 4900 lbm/ft-sec/sup 2/) were analyzed to determine the static rhoV/sup 2/ load needed to cause a buckling failure. The static load needed to cause elastic buckling was found to be equivalent to a rhoV/sup 2/ value of 431,000 lbm/ft-sec/sup 2/ according to classical buckling theory, but could be as low as rhoV/sup 2/ = 100,000 lbm/ft-sec/sup 2/ due to uncertain end fixity and other spring imperfections.
Date: August 4, 1978
Creator: Mosby, W.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Appendix B: Thermal-Hydraulic Data Related To TC-1 Tests

Description: Graphs presenting peak power history, ratio of local rod power to rod average power (P/A), total heat transfer coefficient history, and coolant pressure history conditions in the test assembly during the transient phase of the TC-1 tests.
Date: May 1981
Creator: Yackle, Tom R.; Waterman, Michael E. & MacDonald, Philip E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Appendix C: Fuel Rod Characterization

Description: Tables presenting design variables for TC-1 fuel rods including composite powder analysis, pellet and fuel stack dimensions, and fuel rod and flow shroud dimensions.
Date: May 1981
Creator: Yackle, Tom R.; Waterman, Michael E. & MacDonald, Philip E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Appendix D: Experiment Design and Conduct

Description: Report presenting the design of the Test TC-1 test train and Power Burst Facility (PBF) blowdown system and the test conduct in tables, text, and illustrations.
Date: May 1981
Creator: Yackle, Tom R.; Waterman, Michael E. & MacDonald, Philip E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Assessment of core damadge models in SCDAP/RELAP5 during OECD LOFT LP-FP-2

Description: The US Nuclear Regulatory Commission has sponsored a program to apply the SCDAP/RELAP5 code to analysis of the transient and reflood phases of the OECD LOFT LP-FP-2 Experiment. The principal objectives of the LP-FP-2 experiment were to determine the fission product release from the fuel during the early phases of a severe fuel damage scenario and to examine the phenomena controlling fission product transport in a vapor/aerosol environment. Calculations with the SCDAP/RELAP5 code, developed at t… more
Date: January 1, 1991
Creator: Coryell, E. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Assessment of core damage models in SCDAP/RELAP5 during OECD LOFT LP-FP-2

Description: The US Nuclear Regulatory Commission has sponsored a program to apply the SCDAP/RELAP5 code to analysis of the transient and reflood phases of the OECD LOFT LP-FP-2 Experiment. The principal objectives of the LP-FP-2 experiment were to determine the fission product release from the fuel during the early phases of a severe fuel damage scenario and to examine the phenomena controlling fission product transport in a vapor/aerosol environment. Calculations with the SCDAP/RELAP5 code, developed at t… more
Date: December 31, 1991
Creator: Coryell, E. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Assessment of the influence of surface thermocouples on the behavior of nuclear fuel rods during a large break LOCA

Description: A second series of thermocouple effects tests (TC-3) is being conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory (INEL). These tests are designed to evaluate the influence of external surface thermocouples on the behavior of nuclear fuel rods during a large break loss-of-coolant accident (LOCA) experiment, which includes partial or total rod rewet during blowdown. Questions have been raised with regard to possible effects of surface thermocouples on the the… more
Date: January 1, 1980
Creator: Yackle, T. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Automatic ultrasonic testing and the LOFT in-service inspection program

Description: An automatic ultrasonic testing system has been developed which significantly improves the flaw indication detection and characterization capability over the capability of conventional volumetric examination techniques. The system utilizes an accurately located ultrasonic sensor to generate the examination data. A small computer performs and integrates control and data input/output functions. Computer software has been developed to provide a rigorous method for data analysis and ultrasonic imag… more
Date: January 1, 1980
Creator: Hunter, J.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Behavior of core exit temperature noise RMS in PWRs

Description: Temperature noise measurements were performed at a commercial PWR and the Loss of Fluid Test Facility (LOFT) reactor under varying power levels and core coolant flow rates, producing different core ..delta..Ts. The temperature noise RMS (over the frequency range from 0.1 to 1.0 Hz) is a linear function of core ..delta..T for the commercial PWR. The data encompass a range of 2.8 to 100% power at constant flow. The temperature noise RMS at LOFT is also a linear function of core ..delta..T as show… more
Date: January 1, 1982
Creator: Sweeney, F. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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