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Fuel Thermal Expansion (FTHEXP). [BWR; PWR]

Description: A model is presented which deals with dimensional changes in LWR fuel pellets caused by changes in temperature. It is capable of dealing with any combination of UO/sub 2/ and PuO/sub 2/ in solid, liquid or mixed phase states, and includes expansion due to the solid-liquid phase change. The function FTHEXP models fuel thermal expansion as a function of temperature, fraction of PuO/sub 2/, and the fraction of fuel which is molten.
Date: July 1, 1978
Creator: Reymann, G. A.
Partner: UNT Libraries Government Documents Department

LOFT steady state critical heat flux tests (6. 9 to 13. 8 MPa)

Description: Steady state critical heat flux (CHF) tests have been performed on electrically heated rod bundles simulating the central region of the Loss-of-Fluid Test (LOFT) nuclear reactor core. Previously reported steady state CHF tests have shown that cladding surface thermocouples on LOFT fuel rods reduce the critical heat flux over the pressure range of 13.8 to 16.5 MPa. Reported are additional steady state CHF tests which have been performed to determine the effects of rod external thermocouples on CHF over the ranges of pressure (about 11 MPa) and quality (30 to 40 percent) where CHF is predicted to occur in LOFT during blowdown operation and to determine if sufficient data could be obtained to develop a CHF correlation to predict critical heat fluxes in the LOFT core for blowdown operation.
Date: June 1, 1978
Creator: Gottula, R.C.
Partner: UNT Libraries Government Documents Department

RELAP5 progress summary: simulation of semiscale isothermal blowdown (Test S-01-4A). [RELAP 5/MOD O code]

Description: The RELAP5/MOD''O'' LOCA analysis code has been applied to Simulation of the Semiscale Isothermal Blowdown Test (S-01-4A) from initiation to 60 seconds. Subcooled ECC injection was simulated from 23 seconds until accumulator emptying. The calculated results are in very good agreement with the experimental data. This is the first full system application of the RELAP5 code and only the pressurizer surge line resistance was modified to achieve the results reported. An analysis of the code execution time using a time-step statistical edit is included.
Date: July 1, 1978
Creator: Kuo, H. H.; Wagner, R. J.; Carlson, K. E.; Kiser, D. M.; Trapp, J. A. & Ransom, V. H.
Partner: UNT Libraries Government Documents Department

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

LOFT LOCA: WHAM6 model and code application

Description: This report documents the WHAM6 analysis of a loss-of-coolant accident (LOCA) pipe break at the reactor vessel. Data derived from this document is to be used to generate loads for the LOCA analysis of the reactor internals.
Date: July 27, 1978
Creator: Berta, V.T.
Partner: UNT Libraries Government Documents Department

LOFT advanced densitometer L1-4 test

Description: The report covers the PC-2, C-beam chordal average density measurement made on the loss-of-fluid test (LOFT) primary coolant system hot leg during the L1-4 nonnuclear loss-of-coolant accident (LOCA) test conducted May 3, 1977. The P-2, C-beam, or LOFT advanced densitometer, used was of the pulse height analysis/energy discrimination, or nuclear hardened type to be used for LOFT nuclear tests. The L1-4 test verified the applicability of pulse height analysis/energy discrimination techniques of the nuclear hardened gamma densitometer. Test results show that the reactor coolant fluid chordal average density can be calculated from gamma radiation source signal measured count rate data.
Date: June 28, 1978
Creator: Wood, D.B.
Partner: UNT Libraries Government Documents Department

LOFT reactor vessel 290/sup 0/ downcomer stalk instrument penetration flange stress analysis

Description: The LOFT Reactor Vessel 290/sup 0/ Downcomer Stalk Instrument Penetration Flange Stress Analysis has been completed using normal operational and blowdown loading. A linear elastic analysis was completed using simplified hand analysis techniques. The analysis was in accordance with the 1977 ASME Boiler and Pressure Vessel Code, Section III, for a Class 1 component. Loading included internal pressure, bolt preload, and thermal gradients due to normal operating and blowdown.
Date: June 6, 1978
Creator: Finicle, D.P.
Partner: UNT Libraries Government Documents Department

Fission product inventory, release fractions, and radiation levels from fission products released to the test chamber

Description: The fission product inventory, fission product release fractions, and radiation levels following a blowdown into the test chamber are presented. Operating sequences discussed are based on present knowledge and are used for the purpose of calculating radiation levels at different times.
Date: May 12, 1978
Creator: Maringas, N.
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

LOFT CIS analysis penetration S-11B 12'' H and V duct

Description: The 12 in. H and V Duct and related piping outside the LOFT containment and connected to containment penetration S-11B was analyzed to ASME Code, Subsection NC (Class 2) criteria. This duct is part of the Containment Isolation System. The model considered the duct from the containment O.D. outward through the second isolation valve. Results of this analysis show that this section of the line will meet Class 2 requirements without modification.
Date: July 13, 1978
Creator: Condie, C.G.
Partner: UNT Libraries Government Documents Department

Measurement and control techniques in geothermal power plants

Description: This information provided the background and source material used in preparing the chapter of the Geothermal Source Book on instrumentation, measurement, and control techniques. Here more complete and detailed information is presented than could be included in the source book chapter and is being published for reference. Included are detailed examples of instrumentation and control techniques currently being used in geothermal power plants. In addition, the basic guidelines and unique characteristics of instrumentation and control in geothermal systems, are presented. The instrumentation and control philosophy and the hardware involved in geothermal electric plants and their supply and injection systems are addressed. The intent is to address the unique characteristics of geothermal electric instrumentation and control (I and C) systems. Standard I and C practice is available in the general literature. Sources of information for standard I and C practice are listed in the Appendix. The information presents the philosophy of I and C system design; the development of the system, from power grid considerations through subsystem operation to specific system details; and component selection and operating considerations.
Date: January 1, 1979
Creator: Whitbeck, J.F.; Dart, R.H.; Miller, J.D. & Brewer, D.R.
Partner: UNT Libraries Government Documents Department

Corrosion of copper base alloys in a geothermal brine. SPE Paper No. 7881

Description: The geothermal environment and the experimental procedures and schedules for corrosion tests of copper-base alloys are described. Corrosive attack on these materials was mostly uniform. Some selective leaching of alloying elements was observed, as was crevice corrosion, but the extent of these forms of corrosion was minor. The results of these tests show a trend toward higher corrosion rates with increasing copper content, for the brass alloys. Commercially pure copper, however, showed corrosion rates 20 to 30% of that suggested by the trend in the data. One copper--nickel alloy was tested to verify earlier test data; this alloy showed a corrosion rate about six times that of a brass of similar copper content. The primary agent of the corrosive attack was hydrogen sulfide, present in the water in trace amounts. The primary conclusion from these tests is that copper--zinc alloys are the most economical materials for boiler and preheater construction. The recommendation is made that materials be selected from these brasses: naval brass, yellow brass, admiralty brass, and copper, in this order of decreasing desirability. Aluminum brass and red brass are marginally acceptable. Copper--nickel alloys are unacceptable for boiler and preheater heat exchangers.
Date: January 1, 1979
Creator: Miller, R.L.
Partner: UNT Libraries Government Documents Department

Dispersion in fracture networks

Description: A physical model was built to study the relationship between fracture network characteristics and dispersion of solutes. The study was aimed at evaluating dispersion effects due to differences in the orientation of flow to the fracture network. Radial flow injection tests were conducted at three different flow rates (30, 60, 90 cm/sup 3//min.). Solute break-through was measured with specific conductance probes at 14 orientations to the major axis of the fracture network. Dispersivity coefficients were calculated from breakthrough curves. Results indicated calculated dispersivity coefficients increased with increasing flow rates and were affected by flow orientation to the orthogonal fracture network.
Date: January 1, 1982
Creator: Hull, L.C. & Koslow, K.N.
Partner: UNT Libraries Government Documents Department

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.
Partner: UNT Libraries Government Documents Department

Offsite exposure from failure of waste gas processing system piping failure

Description: A calculation has been performed to determine the offsite exposure to the general public in the unlikely event of the failure of Waste Gas Processing System (WGPS) piping. The consequences for this type of accident are limited by DOEM 0524 with an offsite dose of 1.5 REM. As can be seen in this LTR, the doses from this accident are far in excess of the 0524 limits. Also included in this LTR is a calculation of the BST gas space contents vs. time in the event of a WGPS piping failure.
Date: September 14, 1978
Creator: Swartzwelder, R.B.
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

Technical Specification Figure 3-1, PCS temperature vs. pressure

Description: The bases and procedure for plotting LOFT Technical Specification Figure 3-1, PCS Temperature vs. Pressure is presented. The curves define fracture toughness limits for the carbon steel vessels (Reactor vessel, pressurizer and steam generator) in the primary coolant system (PCS). An allowance is included for the lag between measured fluid temperature and metal temperature of the carbon steel components for the heat up situation. As a result the curves are conservative for the cooldown situation. However, no allowances for expected pressure and temperature instrument errors is included in the curves.
Date: June 6, 1978
Creator: Brown, E.S.
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

Response of RRGI 6 and RRGI 7 to injection during the 5-MW plant operations, March 25 to June 15, 1982, at Raft River, Idaho

Description: Injection testing conducted between March 25 and June 15, 1982 at the Raft River Site generated a substantial quantity of non-isothermal and various temperature transient pressure data. Injection pressure build-up measured at the wellhead strongly responds to temperature changes of the injected fluid. An increase in the fluid temperature results in an injection pressure increase while a temperature decrease is followed by an injection pressure decline. Data analyses indicate that changes in fluid viscosity and density due to temperature changes do not explain pressure build-up responses. The pressure build-up behaviors are attributed to the reservoir transmissivity changes. The absolute wellhead pressure value are significantly lower than predicted for the cold fluid injection.
Date: January 1, 1982
Creator: Skiba, P.A.
Partner: UNT Libraries Government Documents Department