198 Matching Results

Search Results

Advanced search parameters have been applied.

Stress analysis of the LOFT modular DTT flowmeter for LOCE transients (L1-5 and L2-4)

Description: An analysis is presented of combined stresses in the LOFT Modular DTT for specified temperature gradients. All combined stress intensities are shown to stay within applicable allowable stress intensities. A fatigue analysis is also presented which indicates that the LOFT Modular DTT will withstand 70,000 blowdown cycles. The LOFT Modular DTT is shown to meet the Class 1 stress requirments. A stress analysis of the tab region of the newly designed MDTT tab-type shroud is included. This stress analysis shows that the Class 1 stress requirements are met by the tab-type MDTT shroud design and that this design imposes no fatigue life limitation on the MDTT.
Date: August 16, 1978
Creator: Mosby, W.R.
Partner: UNT Libraries Government Documents Department

Summary and results of the comprehensive environmental monitoring program at the INEL's Raft River geothermal site

Description: The Raft River Geothermal Program was designed to demonstrate that moderate temperature (approx. 150/sup 0/C) geothermal fluids could be used to generate electricity and provide an alternate energy source for direct-use applications. The environmental program was initiated soon after drilling began. The major elements of the monitoring program were continued during the construction and experimental testing of the 5-MW(e) power plant. The monitoring studies established pre-development baseline conditions of and assessed changes in the physical, biological, and human environment. The Physical Environmental Monitoring Program collected baseline data on geology, subsidence, seismicity, meteorology and air quality. The Biological Environmental Monitoring Program collected baseline data on the flora and fauna of the terrestrial ecosystem, studied raptor disturbances, and surveyed the aquatic communities of the Raft River. The Human Environmental Monitoring Program surveyed historic and archaeological sites, considered the socioeconomic environment, and documented incidences of fluorosis in the Raft River Valley. In addition to the environmental monitoring programs, research on biological direct applications using geothermal water was conducted at Raft River. Areas of research included biomass production of wetland and tree species, aquaculture, agricultural irrigation, and the use of wetlands as a treatment or pretreatment system for geothermal effluents.
Date: January 1, 1982
Creator: Mayes, R.A.; Thurow, T.L. & Cahn, L.S.
Partner: UNT Libraries Government Documents Department

Similarities and differences in vapor explosion criteria

Description: An overview of recent ideas pertaining to vapor explosion criteria indicates that in general sense, a consensus of opinion is emerging on the conditions applicable to explosive vaporization. Experimental and theoretical work has lead a number of investigators to the formulation of such conditions which are quite similar in many respects, although the quantitative details of the model formulation of such conditions are somewhat different. All model concepts are consistent in that an initial period of stable film boiling, separating molten fuel from coolant, is considered necessary (at least for large-scale interactions and efficient intermixing), with subsequent breakdown of film boiling due to pressure and/or thermal effects, followed by intimate fuel-coolant contact and a rapid vaporization process which is sufficient to cause shock pressurization. Although differences arise as to the conditions for and the energetics associated with film boiling destabilization and the mode and energetics of fragmentation and intermixing. However, the principal area of difference seems to be the question of what constitutes the requisite condition(s) for rapid vapor production to cause shock pressurization.
Date: January 1, 1978
Creator: Cronenberg, A.W.
Partner: UNT Libraries Government Documents Department

Test prediction for the German PKL test K5A using RELAP4/MOD6. [PWR]

Description: RELAP4/MOD6 is a computer code developed specifically to predict the transient thermal-hydraulic behavior of a PWR and related experimental reactor systems during reflood phase of postulated LOCA conditions. A ''blind'' test prediction for the German PKL reflood Test K5A was conducted using RELAP4/MOD6. The results of the prediction were in good agreement with experimental data indicating that RELAP4/MOD6 is capable of predicting transient reflood phenomena in the 200 percent cold-leg break test configuration of the PKL reflood facility.
Date: January 1, 1978
Creator: Chen, Y.S.; Haigh, W.S.; Sullivan, L.H. & Fischer, S.R.
Partner: UNT Libraries Government Documents Department

Sensitivity study of main steam flow control valve closing and opening times

Description: The sensitivity of the LOFT plant to different main steamflow control valve closure and opening times is examined using a hybrid computer simulation. Results for seven valve opening rates and seven valve closing rates are presented and discussed. Comparisons are made between this analysis and the current FSAR which assumes a 20 second full stroke motion rate. While full-stroke valve motion times of 1 to 40 seconds are shown to be acceptable with respect to safety margins, a motion time of 10 to 30 seconds is recommended to allow for adequate control sensitivity.
Date: March 1, 1978
Creator: Tylee, J.L.
Partner: UNT Libraries Government Documents Department

Geothermal energy market potential in industrial processing

Description: Geothermal energy is currently being used for a number of industrial processes in countries throughout the world. Its application in the United States is mainly limited to space heating even though the temperature of the geothermal fluid is sufficient for process uses, and could be sold at attractive prices while maintaining a high return on investment. The temperature span for industrial use ranges from 40 to 275/sup 0/C, thus encompassing both the abundant low temperature and the less available high temperature resources. Hydrothermal fluids can be used either directly or indirectly dependent upon fluid quality and process needs. The barriers facing hydrothermal industrial process development are (a) the development infrastructure does not exist, (b) energy users are not aware of hydrothermal energy and its advantages, (c) federal incentives are limited, (d) resources are not fully defined.
Date: November 1, 1978
Creator: Schultz, R.J.; Hanny, J.A. & Knuth, W.H.
Partner: UNT Libraries Government Documents Department

Evaluation of the effect of break nozzle configuration in loss-of-coolant accident analysis

Description: The Semiscale Mod-1 test program has utilized two different break nozzle configurations in a test facility with identical initial and boundary conditions. An evaluation has been made to determine the effect these break nozzle configurations have on system thermal-hydraulic response during a 200% double-ended cold leg break loss-of-coolant accident simulation. The first nozzle had a convergent-divergent design; the second nozzle had a convergent design with an elongated constant area throat followed by a rapid expansion. Analysis of data from tests conducted with the two nozzles shows that the critical flow characteristics at the break plane were affected by the break nozzle geometry. Differences in break flow caused differences in the core inlet flow which in turn affected core heater rod thermal response. The results of this investigation show that the break flow behavior and the resulting core thermal response in the Semiscale experimental facility can be directly correlated.
Date: January 1, 1979
Creator: Hanson, R G
Partner: UNT Libraries Government Documents Department

Some factors affecting the metering of subcooled water with a choked venturi

Description: A series of experiments was performed to characterize the subcooled choking process in a convergent-divergent nozzle with a constant-area throat. The experiments were conducted in a low-pressure flow loop capable of a maximum water flow rate of 5.5 L/s with a pressure head of 300 kPa. The pressure and temperature upstream of the nozzle in the flow loop were adjusted between 90 and 300 kPa and 53 and 96/sup 0/C, respectively. The variables measured in this study of critical flow phenomena were the flow rate, upstream pressure and temperature, and the axial wall pressure profiles in the nozzle. Critical mass flow rate data were acquired along five isotherms as a function of stagnation pressure. Factors affecting metering performance are examined.
Date: January 1, 1981
Creator: Fincke, J.R. & Collins, D.R.
Partner: UNT Libraries Government Documents Department

Self-initialization module for the RELAP4/MOD7 program

Description: An automated self-initialization option has been developed and implemented into the RELAP4/MOD7 computer code. With this new feature, pressurized water reactors or similar models may be initialized to steady state conditions with minimal user-supplied input data. Previously, the analyst (user) had to hand compute all pressures and temperatures in conjunction with several iterative computer runs. Two semi-independent functions, pressure balancing and thermal balancing, comprise the self-initialization module. The user supplies input data specifying a reference pressure and temperature and associated locations. Control volume pressures and temperatures are computed consistent with the nodalization, geometry, total power, and mass flow rates specified. Verification has been accomplished by performing transient calculations on system models and observing the persistence of stable operating conditions. Preparation of input data for the self-initialization module seldom requires more than several man-hours. Computing time required on a CDC 7600 computer to complete the self-initialization process is typically less than 30 seconds.
Date: January 1, 1979
Creator: Behling, S.R.; Burgess, C.H. & Johnsen, G.W.
Partner: UNT Libraries Government Documents Department

TRAC-BD1: transient reactor analysis code for boiling-water systems

Description: The Boiling Water Reactor (BWR) version of the Transient Reactor Analysis Code (TRAC) is being developed at the Idaho National Engineering Laboratory (INEL) to provide an advanced best-estimate predictive capability for the analysis of postulated accidents in BWRs. The TRAC-BD1 program provides the Loss of Coolant Accident (LOCA) analysis capability for BWRs and for many BWR related thermal hydraulic experimental facilities. This code features a three-dimensional treatment of the BWR pressure vessel; a detailed model of a BWR fuel bundle including multirod, multibundle, radiation heat transfer, leakage path modeling capability, flow-regime-dependent constitutive equation treatment, reflood tracking capability for both falling films and bottom flood quench fronts, and consistent treatment of the entire accident sequence. The BWR component models in TRAC-BD1 are described and comparisons with data presented. Application of the code to a BWR6 LOCA is also presented.
Date: January 1, 1981
Creator: Spore, J.W.; Weaver, W.L.; Shumway, R.W.; Giles, M.M.; Phillips, R.E.; Mohr, C.M. et al.
Partner: UNT Libraries Government Documents Department

Semiannual progress report for the Idaho Geothermal Program, April 1--September 30, 1978

Description: Research and development performed by the Idaho Geothermal Program between April 1 and September 30, 1978 are discussed. Well drilling and facility construction at the Raft River geothermal site are described. Efforts to understand the geothermal reservoir are explained, and attempts to predict the wells' potential are summarized. Investigations into the direct uses of geothermal water, such as for industrial drying, fish farming, and crop irrigation, are reported. The operation of the facility's first electrical generator is described. Construction of the first 5-megawatt power plant is recounted. The design effort for the second pilot power plant is also described. University of Utah work with direct-contact heat exchangers is outlined. Special environmental studies of injection tests, ferruginous hawks, and dental fluorisis are summarized. The regional planning effort for accelerated commercialization is described. Demonstration projects in Oregon, Utah, and South Dakota are noted. A bibliographical appendix lists each internal and external report the Idaho Geothermal Program has published since its beginning in 1973.
Date: November 1, 1978
Creator: Blake, G.L. (ed.)
Partner: UNT Libraries Government Documents Department

PSMG sets A and B protective relaying

Description: The ''TAN/LOFT 13.8 kV, 2.4 kV, and 480 V Relay and Circuit Breaker Coordination Study'' presented an analysis to determine overcurrent settings for the LOFT Power System protective relays including those for the drive motors of the PSMG sets. This LTR is written to form the basis of the relay settings entered in Specification ES-60238 Rev. B, for protection of the PSMG generator, primary coolant pump motor and interconnecting power cable. A momentary commercial power voltage dip occurred on January 10, 1978 which caused a trip of the PSMG field breakers. A corrective design to prevent reoccurrence is discussed and recommendations are presented.
Date: July 24, 1978
Creator: Burnett, J.E.
Partner: UNT Libraries Government Documents Department

Stress analysis of LOFT Emergency Core Coolant System modification (left and right side)

Description: A stress analysis has been performed on proposed modifications to the Emergency Core Coolant System right and left side. For the right side thermal expansion and seismic loads were considered. Results of a previous report using dead weight, design LOCE, and LOCA loads were treated as valid and not repeated here. For the left side LOCE loading only was considered. The results of a previous analysis using dead weight, thermal, and LOCE loads were treated as valid and again not repeated here. Review of the analysis indicated that both proposed modifications pass the requirements of the ASME Boiler and Pressure Vessel Code Section III for Class 1 and 2 piping.
Date: August 31, 1978
Creator: Kido, C.
Partner: UNT Libraries Government Documents Department

LOFT reflood as a function of accumulator initial gas volume

Description: The effect of the initial gas volume in the LOFT accumulators on the time to start of core reflood, after a LOCA, has been studied. The bases of the calculations are the data used and results presented in the Safety Analysis Report, Rev.1, August 1977, and the data in the RELAP and TOODEE2 program input and output listings. The results of this study show that an initial nitrogen volume of 12 cu ft, or more (at 600 psig initial pressure), would cause start of core reflood in time to prevent the cladding temperature from reaching 2200/sup 0/F. The 12 cu ft initial volume will expand from 600 psig, initial pressure, to about 10 psig (containment pressure shortly after start of LOCA is approximately 8 psig) when all ECC liquid has been expelled from the accumulator. This pressure margin is considered too small; the ECC flowrate will be zero before the accumulator is empty.
Date: June 1, 1978
Creator: Rhodes, H.F.
Partner: UNT Libraries Government Documents Department

Stress analysis of the LOFT core barrel for LOCA + SSE loads

Description: The results of a dynamic analysis of the LOFT Reactor Core Barrel for faulted conditions are presented in this report. Loading conditions considered were seismic accelerations resulting from a Safe Shutdown Earthquake (SSE) and pressure loadings from both a hot leg and a cold leg Loss-of-Coolant Accident (LOCA) break. Maximum stresses in the core barrel, resulting from these conditions, are presented with comparisons to Code allowables. Stresses were found to be within allowables for the faulted condition as defined in the ASME Code (1977), Appendix F.
Date: July 7, 1978
Creator: Blandford, R.K.
Partner: UNT Libraries Government Documents Department

Pellet-cladding mechanical interaction in Halden Assembly IFA-226

Description: Instrumented Fuel Assembly (IFA) 226 was a (U,PU)O/sub 2/ fueled and zircaloy clad assembly which operated in the Halden Boiling Water Reactor, Halden, Norway, to a peak burnup in excess of 40,000 MWd/t. The assembly was instrumented with fuel rod elongation sensors to continuously monitor pellet-cladding mechanical interaction (PCMI) in selected fuel rods. The elongation behavior of these rods was evaluated to assess the influence of fabrication and irradiation variables on PCMI. The PCMI behavior at startup is contrasted with PCMI at high exposures. Observations on fuel fracture, fuel conditioning, axial racheting, ramp rate, strain relaxation, fuel swelling, and zircaloy growth, and their effects on PCMI, are included.
Date: August 1, 1978
Creator: Owen, D.E.
Partner: UNT Libraries Government Documents Department

Dry scram evaluation

Description: The analysis performed by Todd Shipyards concerning the ability of the LOFT CRDMs to withstand a dry scram is presented. A ''dry scram'' could result in the CRDM components yielding; however, it would probably not render the CRDMs inoperable. It also concluded that a dry scram is highly unlikely based on a typical LOFT depressurization curve and the temperature of the fluid in the upper pressure housing. At the time of scram, the fluid in the upper pressure housing will not flash to steam owing to the pressure-temperature relationship existing during the scram cycle.
Date: June 6, 1978
Partner: UNT Libraries Government Documents Department

Idaho National Engineering Laboratory: Annual report, 1986

Description: The INEL underwent a year of transition in 1986. Success with new business initiatives, the prospects of even better things to come, and increased national recognition provided the INEL with a glimpse of its promising and exciting future. Among the highlights were: selection of the INEL as the preferred site for the Special Isotope Separation Facility (SIS); the first shipments of core debris from the Three Mile Island Unit 2 reactor to the INEL; dedication of three new facilities - the Fluorinel Dissolution Process, the Remote Analytical Laboratory, and the Stored Waste Experimental Pilot Plant; groundbreaking for the Fuel Processing Restoration Facility; and the first IR-100 award won by the INEL, given for an innovative machine vision system. The INEL has been assigned project management responsibility for the SDI Office-sponsored Multimegawatt Space Reactor and the Air Force-sponsored Multimegawatt Terrestrial Power Plant Project. New Department of Defense initiatives have been realized in projects involving development of prototype defense electronics systems, materials research, and hazardous waste technology. While some of our major reactor safety research programs have been completed, the INEL continues as a leader in advanced reactor technologies development. In April, successful tests were conducted for the development of the Integral Fast Reactor. Other 1986 highlights included the INEL's increased support to the Office of Civilian Radioactive Waste Management for complying with the Nuclear Waste Policy Act of 1982. Major INEL activities included managing a cask procurement program, demonstrating fuel assembly consolidation, and testing spent fuel storage casks. In addition, the INEL supplied the Tennessee Valley Authority with management and personnel experienced in reactor technology, increased basic research programs at the Idaho Research Center, and made numerous outreach efforts to assist the economies of Idaho communities.
Date: January 1, 1986
Partner: UNT Libraries Government Documents Department

Fatigue life of LOFT reactor vessel components

Description: This report provides calculated LOCE lifetimes of the LOFT reactor vessel components. For each component, lifetime is defined as the greatest number of LOCE transient cycles and/or other non-LOCE transient cycles such that cumulative usage factor does not exceed 1.0. The results are presented in tabular form. The results indicate that transients other than LOCE transients govern with or instead of LOCE transients for some components. The other transients are shown in the results.
Date: October 31, 1978
Creator: Kido, C. & Murdock, S.M.
Partner: UNT Libraries Government Documents Department