Nuclear Production of Hydrogen, Fourth Information Exchange ...

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ALTERNATE VHTR/HTE INTERFACE FOR MITIGATING TRITIUM TRANSPORT AND STRUCTURE CREEP Introduction The production of hydrogen using nuclear power faces two technical challenges at the interface between the chemical plant and the nuclear plant. As presently envisioned, an intermediate heat exchanger transfers heat from the reactor system at a temperature of 850°C and a pressure of several MPa to a process heat loop where it is then transported over a piping run of the order 100 m to the process heat application. Recent work has identified two challenges at the interface. The use of metals as structural materials and their associated creep at these elevated service conditions limits the lifetime of process heat loop components to less than a nominal nuclear plant lifetime of 40 years. One potential solution is the use of ceramics in place of metals but their reliability for heat exchangers application is as yet unproven. The second challenge involves the migration of tritium from the reactor core through the process heat loop into the chemical plant. It has been suggested that equilibrium levels of tritium in the primary system combined with the permeability of metals at high temperature can result in tritium levels in the chemical plant above what NRC limits permit for non-nuclear systems (Sherman, 2007). Ceramic heat exchangers have the potential to significantly limit tritium transport but again the caveat above applies. This paper describes an approach for solving these challenges in the very high temperature reactor (VHTR) coupled to the high temperature electrolysis plant (HTE). The key is to lower the temperature of the process heat delivered to the chemical plant in a way that does not reduce the efficiency of the coupled plant. An alternative equipment configuration that achieves this is based on the observation that about nine-tenths of the thermal power input to the HTE plant is used to boil water at the relatively low temperature of 247°C. One notes that optimal efficiency of the combined plant is achieved by properly matching the temperature of available heat sources to the temperature at which heat is required. If a process is supplied with heat at a temperature greater than needed to achieve acceptable heat flux, then an unproductive temperature drop occurs and with it a lost ability to do work. In a reference combined plant design, reactor outlet heat at 850°C is used to supply the 247°C heat requirement described above. But a more efficient use of reactor heat is to obtain the 247°C heat at a point in the cycle better matched in temperature. Then the HTE plant heat requirements are met without significant loss of work potential and as a result efficiency increases. In the VHTR/HTE plant the required temperature of 247°C is close to the 130°C temperature at which waste heat is rejected by the PCU. The alternate interface (AI) proposed in this paper uses a low temperature process heat loop in place of the high temperature loop in the reference interface as defined below. The loop operates in heat pump mode taking low quality heat from the PCU and supplying it to the HTE plant to achieve the reactant phase change referred to above. The remaining one-tenth of the needed HTE process heat superheats reactants to about 800°C. In the alternate interface in the absence of a high temperature process heat loop coming from the nuclear plant this heat is supplied by electrical heaters or hydrogen burners. The efficiency of a coupled nuclear-hydrogen plant with the alternate interface is compared against the same for the reference interface. The effects of the alternative interface on combined plant availability, reliability, and maintenance costs and on component longevity are then discussed. Reference interface The reference interface is shown in overview in Figure 1. In this figure the combined plant appears as three modules: the primary system, the power conversion system and the high temperature electrolysis plant. The lines connecting these three modules represent the interface. Each of these three modules is shown in greater detail in Figures 2 through 4. Note the high temperature process heat loop shown in Figure 1. The hot side operates at a temperature of about 890°C and contains a path for tritium passing across the IXH to make its way to the HTE plant. The performance of the reference interface is characterised in Vilim (2007). In that work the GPASS/H code was used to determine the full power condition, the combined plant efficiency and the partial power load schedule. The values of the main operating parameters are summarised in Table 1. 434 NUCLEAR PRODUCTION OF HYDROGEN – © OECD/NEA 2010
ALTERNATE VHTR/HTE INTERFACE FOR MITIGATING TRITIUM TRANSPORT AND STRUCTURE CREEP Figure 1: Combined plant with reference interface Figure 2: High temperature electrolysis plant Figure 3: Reference power conversion unit plant NUCLEAR PRODUCTION OF HYDROGEN – © OECD/NEA 2010 435
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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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Page 390 and 391: CONCEPTUAL DESIGN OF THE HTTR-IS NU
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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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