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ALTERNATE VHTR/HTE INTERFACE FOR MITIGATING TRITIUM TRANSPORT AND STRUCTURE CREEP and System Simulator (GPASS) code. At full power one is interested in knowing the efficiency of the combined plant and the temperatures at the interface. At partial power one is interested in how temperatures change with load. Full power The temperatures and pressures in the low temperature process heat loop of the alternate interface are compared in Table 2 with those in the high temperature process heat loop of the reference interface. One sees that for the heat exchanger coupling the process heat loop to the source of heat in the nuclear plant the temperatures have been significantly reduced. They have dropped on average from 800°C to 200°C. The reduction decreases the diffusion rate of tritium through the heat exchanger heat transfer surfaces by about a factor of 100. One also sees that all temperatures in the low temperature loop are below 500°C. As a consequence more economical steels can be used in place of those alloys needed in the case of the high temperature loop that operates at 850°C. Table 2: Comparison of conditions in main process heat loops Condition Temperature, C Hot side in Hot side out Cold side in Cold side out Pressure, MPa Hot side Cold side Source heat exchanger RI [6] AI (HTLHX) (PCU boiler) 870 611 515 849 7.2 1.8 231 214 160 179 2.6 0.6 Sink heat exchanger RI [6] (HTE boiler) 488 332 184 247 1.8 5.0 AI (HTE boiler) 480 286 184 247 7.0 5.0 The alternate interface still requires a high temperature heat source to power the heat exchanger HX2 in Figure 2. However, this heat source is now envisioned to be electrical heaters or a hydrogen or natural gas combustor in place of reactor heat. The link to the reactor has been broken allowing for improved temperature control and limiting HX2 to a role as an accident initiator in the chemical plant rather than the combined plant. The efficiency of the plant with the alternate interface is at least 1.5% higher. The increase is a consequence of better matching of heat source temperature to HTE plant heat requirements. The power sources and sinks that combine to determine the overall efficiency are shown in Table 3. It is noted that substituting combustion of a synthetic organic created from the plant hydrogen stream in place of electric heating might raise the efficiency of the Alternate Interface plant another 1%. Control system A principle objective in developing a control strategy for partial-load operation is to maintain temperatures constant with power over the normal operation power range, particularly hot-end temperatures. Another consideration is that peak efficiency should by design occur at full power since the plant is to operate there for the largest fraction of life. While partial load efficiency is important, maintaining constant temperatures over load at the hot end is probably more important since material capabilities at 900°C are a limiting factor in plant lifetime. The focus of the control strategy in this work was therefore on maintaining constant hot-end temperatures. Partial power operation takes place over a continuum and is constrained by the load schedule. The load schedule specifies the value of each process variable as a function of plant power. Good operability as characterised by minimal thermal stresses during power change is achieved by developing a load schedule that maintains temperatures constant with respect to load at the hottest points in the plant (e.g. reactor outlet). The control strategy developed in this work makes use of the principle that the temperature change from inlet to outlet in a heat exchanger remains constant when the mass flow rate and power 440 NUCLEAR PRODUCTION OF HYDROGEN – © OECD/NEA 2010
ALTERNATE VHTR/HTE INTERFACE FOR MITIGATING TRITIUM TRANSPORT AND STRUCTURE CREEP Table 3: Summary of power and efficiency by interface type Powers in MWt Plant interface Reference Alternate Reactor primary system Primary compressor -7.0 -8.1 Power conversion unit and intermediate system Turbine (PCU) HP compressor (PCU) LP compressor (PCU) Aux. HP compressor (PCU) Intermediate system compressor +534 -126 -127 n.a. -0.9 +576 -130 -105 -36 n.a. Process heat loop Process heat loop compressor -7.0 -12 High temperature electrolysis plant Cell electrical power Electrical heating of reactants Turbine (HTE) Other pumps and compressors Hydrogen LHV -288 n.a. +11.5
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Nuclear Science 2010 Nuclear Produc
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ORGANISATION FOR ECONOMIC CO-OPERAT
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TABLE OF CONTENTS Table of contents
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TABLE OF CONTENTS Y. Gong, E. Chalk
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EXECUTIVE SUMMARY Executive summary
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EXECUTIVE SUMMARY steam turbine, in
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EXECUTIVE SUMMARY sulphur depositio
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EXECUTIVE SUMMARY affords saving 35
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EXECUTIVE SUMMARY safety assessment
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EXECUTIVE SUMMARY The question was
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CHANGING THE WORLD WITH HYDROGEN AN
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NUCLEAR HYDROGEN PRODUCTION PROGRAM
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NUCLEAR HYDROGEN PRODUCTION PROGRAM
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FRENCH RESEARCH STRATEGY TO USE NUC
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PRESENT STATUS OF HTGR AND HYDROGEN
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STATUS OF THE KOREAN NUCLEAR HYDROG
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THE CONCEPT OF NUCLEAR HYDROGEN PRO
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CANADIAN NUCLEAR HYDROGEN R&D PROGR
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APPLICATION OF NUCLEAR-PRODUCED HYD
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STATUS OF THE INL HIGH-TEMPERATURE
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HIGH-TEMPERATURE STEAM ELECTROLYSIS
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MATERIALS DEVELOPMENT FOR SOEC Mate
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A METALLIC SEAL FOR HIGH-TEMPERATUR
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DEGRADATION MECHANISMS IN SOLID OXI
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CAUSES OF DEGRADATION IN A SOLID OX
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70 μm CAUSES OF DEGRADATION IN A S
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NUCLEAR HYDROGEN USING HIGH TEMPERA
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SESSION III: THERMOCHEMICAL SULPHUR
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CEA ASSESSMENT OF THE SULPHUR-IODIN
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STATUS OF THE INERI SULPHUR-IODINE
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INFLUENCE OF HTR CORE INLET AND OUT
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EXPERIMENTAL STUDY OF THE VAPOUR-LI
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DEVELOPMENT OF HI DECOMPOSITION PRO
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SOUTH AFRICA’S NUCLEAR HYDROGEN P
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INTEGRATED LABORATORY SCALE DEMONST
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DEVELOPMENT STATUS OF THE HYBRID SU
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RECENT CANADIAN ADVANCES IN THE THE
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AN OVERVIEW OF R&D ACTIVITIES FOR T
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STUDY OF THE HYDROLYSIS REACTION OF
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DEVELOPMENT OF CuCl-HCl ELECTROLYSI
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EXERGY ANALYSIS OF THE Cu-Cl CYCLE
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CaBr 2 HYDROLYSIS FOR HBr PRODUCTIO
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SESSION V: ECONOMICS AND MARKET ANA
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DEVELOPMENT OF THE HYDROGEN ECONOMI
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NUCLEAR H 2 PRODUCTION - A UTILITY
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ALKALINE AND HIGH-TEMPERATURE ELECT
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THE PRODUCT OF HYDROGEN BY NUCLEAR
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SUSTAINABLE ELECTRICITY SUPPLY IN T
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PROHYTEC, THE FRENCH INDUSTRIAL PLA
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NHI ECONOMIC ANALYSIS OF CANDIDATE
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MARKET VIABILITY OF NUCLEAR HYDROGE
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POSSIBILITY OF ACTIVE CARBON RECYCL
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NUCLEAR SAFETY AND REGULATORY CONSI
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TRANSIENT MODELLING OF S-I CYCLE TH
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PROPOSED CHEMICAL PLANT INITIATED A
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CONCEPTUAL DESIGN OF THE HTTR-IS NU
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Page 409 and 410: HEAT PUMP CYCLE BY HYDROGEN-ABSORBI
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Page 420 and 421: HEAT EXCHANGER TEMPERATURE RESPONSE
Page 435 and 436: ALTERNATE VHTR/HTE INTERFACE FOR MI
Page 441: ALTERNATE VHTR/HTE INTERFACE FOR MI
Page 447: POSTER SESSION CONTRIBUTIONS Poster
Page 450 and 451: ACTIVITIES OF NUCLEAR RESEARCH INST
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Page 459: MEETING ORGANISATION Annex 1: Meeti
Page 462 and 463: LIST OF PARTICIPANTS REYTIER, Magal
Page 464 and 465: LIST OF PARTICIPANTS BROWN, Nichola
Page 466: LIST OF PARTICIPANTS SINK, Carl US
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