AREVA Solar has designed, constructed and demonstrated the first successful Once Through Solar Steam Generator (SSG) to deliver superheated steam without intermediate heat transfer fluids. Deployed at the Kimberlina Solar Thermal Power Station, SSG4 represents the state of the art for solar steam production, for stand-alone power generation and augmentation of fossil fueled steam cycles. The ASME Section I boiler was designed, constructed, stamped and commissioned during 2010, and includes a novel Model Predictive Control system capable of maintaining any two of three steam conditions (flow, pressure, temperature) under varying solar input. During field trials in September 2010, exit steam conditions were maintained at 60 +/− 3 bar and 370 +/− 20C during steady and transient conditions, while steam flow consistently exceeded predictions. In a “lights-out” test, simulating complete instantaneous cloud cover, SSG4 had sufficient thermal inertia to supply more than 18 minutes of superheated steam. AREVA Solar’s SSGs incorporate a 400m long tube bundle within an elevated insulated cavity receiver, onto which sunlight is concentrated by reflectors. The multi-pass tube bundle arranges superheater tubes in the high flux regions, and economizer/evaporator tubes in lower flux regions. This assures sufficient heat flux to sustain superheated steam temperatures throughout the operating day, and also reduces the average bundle temperature to reduce radiant heat losses. Boiler tubes were prepared in AREVA Solar’s factory to improve their absorption of solar energy and reduce radiant heat losses. The inverted cavity maintains a stagnant air layer between the tube bundle and a glass cover below the boiler tube supports, to reduce convective heat loss. SSG4 was designed for a Maximum Allowable Working Pressure of 105 bara, and a Maximum Mean Wall Temperature of 482C in the superheater section. AREVA Solar is the first Concentrated Solar Power provider with an ASME “S” Stamp and National Board authorization. Following the initial trials at 370C, the SSG is expected to operate at 450C superheated steam temperature. This paper describes the design, construction, commissioning, and testing of the Compact Linear Fresnel Reflector (CLFR) SSG4.
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i A rising level of' scrutiny is being directed toward the Savannah River Site (SRS) production reactors. Improved calculational capabilities are being developed to provide a best estimate analytical process to determine the safe operating margins of the reactors. The Code Scaling, Applicability, and Uncertainty (CSAU) methodology, developed by the U. S. Nuclear Regulatory Commission to support best estimate simulations, is being applied to the best estimate limits analysis for the SRS production reactc-s. One of the foundational parts of the method is the identification and ranking of ali the processes that occur during the specific limiting scenario. The phenomena ranking is done according to their importance to safety criteria during the transient and is used to focus the tmcerminty analysis on a sufficient, yet cost effective scope of work. This report documents the thermal-hydraulic phenomena that occur during a limiting break in an SRS production reactor and their importance to the uncertainty in simulations of the reactor behavior.ii II SUMMARY .0The _ scrutiny directed toward the operation of Department of Energy production reactors in recent years has led to the development and incorporationof best-estimate computer codes in the safety analysis process. The use of best-estimate techniques requires that the analysis be accompanied by a quantification of the uncertainty in the calculated restdts. The operating power limit for the SRS production reactors is determined through the use of computer codes. The CSAU methodology, developed by the U. S. Nuclear Regulatory Commission to support best estimate analyses for light water reactors,is being applied to the power limiting transientfor the SRS production reactors.The first segment in _e CSAU methodology is the identification and ranking of phenomena that are imtxn'tant to the limiting scenario. Since it is not cost effective to assess ali models in the code the CSAU method provides justification for investigating only the important phenomena. The selection is made according to a ranking of the importance the phenomena have with respect to safe reactor operations. The purpose of this report is to identify the thermal-hydraulic phenomena associated with the limiting break in an SRS production reactor and their importance to the safety criteria used to establish acceptable safety margins.
This report documents ten developmentalassessmentproblems which were " used to test the multidimensionalcomponent in RELAP5/MOD2.5,Version 3w. The problems chosen were a rigid body rotation problem, a pure radial symmetric flow problem, an r-0 symmetric flow problem, a fall problem, a rest problem, a basic one-dimensionalflow test problem, a gravity wave problem, a tank draining problem, a flow through the center problem, and coverage analysis using PIXIE. The multidimensionalcode calculationsare compared to analytical solutions and one-dimensionalcode calculations. The discussion section of each problem contains informationrelative to the code's ability to simulate these problems. iii Idaho, Inc., managers during the development and assessment of this capabilitywho provided coordination,direction,and resources.
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