atw 2018-04v6

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atw Vol. 63 (2018) | Issue 4 ı April OPERATION AND NEW BUILD 220 | | Fig. 8. Schematic of the General Nuclear Reactor (GNR) model [1]. Being able to model all kinds of heat transfer accurately and to include fission physics makes the software a valuable tool for every nuclear engineer and power cycle developer. Figure 9 shows an integrated simulation model that includes a reactor, steam generator, heat exchange, and some turbomachinery. Summary In order to size control valves or determine the control strategy for a loop, it is necessary to have the pump performance curve, the heat exchanger pressure drop and heat transfer characteristics as well as reactor dynamic behaviour in one simulation model. In this article, a fast and efficient solution for designing many types of heat transfer systems is presented. It was shown how to model any setup and kind of heat exchanger such as plate, tubein-tube, liquid/gas, finned tube etc. Flownex® Simulation Environment offers a straight-forward workflow for engineers who are involved in designing auxiliary systems that usually contain one or more heat exchangers, such as in the power plant industry. The software is a specialized software (e.g. used by ITER, X Energy, BATAN, Hyundai Heavy Industries) for sizing specific types of heat exchangers or for doing basic steady-state and transient mass-and-energy balances. The value of the software in this area is that one can really integrate the information from all available sources into a single representative model, where one can size all kind of devices, test control strategies, and do integrated system-level analysis and design. Furthermore, examples from the nuclear power plant industry, namely the Koeberg PWR steam generator and the Hamm-Uentrop THTR-300 steam generator which demonstrated the software’s usability for nuclear related work were shown. In addition, the lately incorporated Generic Nuclear Reactor model was introduced. Further Reading | | Flownex® SE: www.flownex.de | | M-Tech Industrial: www.mtechindustrial.com | | Idaho National Laboratory: www.inl.gov References [1] Flownex (2017) User Manual. [2] Van Antwerpen, H.: Design and Optimization of Advanced Nuclear Technologies with 1-d Simulation. 7 th Annual International SMR and Advanced Reactor Summit 2017, 30-31 March, Atlanta, GA, USA. [3] Esch, M., Hurtado, A., Knoche, D., and Tietsch, W.: Analysis of the Influence of Different Heat Transfer Correlations for HTR Helical Coil Tube Bundle Steam Generators with the System Code TRACE. Nuclear Engineering and Design, 251, 374-380, 2012. [4] Van Antwerpen, H., Chi, H., Brits, Y., and Botha, F.: Plant-Wide Simulation Model for Transient Studies on the Xe-100. 2016 ANS Winter Meeting and Nuclear Technology Expo, 6-10 November 2016, Las Vegas, NV, USA. Authors Sebastian Vlach Leiter Marketing & Vertrieb Christoph Fischer (PhD) CFX Berlin Software GmbH Berlin, Germany Herman van Antwerpen (PhD) M-Tech Industrial (Pty) Ltd South Africa | | Fig. 9. Layout of a complete plant power cycle with an example reactor geometry input map (left) [4]. Operation and New Build Heat Transfer Systems for Novel Nuclear Power Plant Designs ı Sebastian Vlach, Christoph Fischer and Herman van Antwerpen
atw Vol. 63 (2018) | Issue 4 ı April Experimental and Analytical Tools for Safety Research of GEN IV Reactors G. Mazzini, M. Kyncl, Alis Musa and M. Ruscak Current research on nuclear safety in the world, in addition to supporting existing nuclear power plants (PLEX, mitigation of severe accidents, the development of accident tolerant fuel, decommissioning, etc.), is focused on the more detailed aspects of the new reactors. The new generation reactors are expected inter alia to use innovative types of fuel and new types of coolants, such as e.g. Super-Critical Water (SCW), supercritical CO 2 , liquid metals, fluoride salts or high-temperature Helium. The paper will describe new experimental infrastructure build recently in Research Centre Řež under the SUSEN (Sustainable Energy) project and available analytical tools for supporting safety research of GEN IV reactors. Two experimental loops - SCWL (Supercritical Water Loop) and HTHL (High Temperature Helium Loop) will serve as in-pile loops in the active core of the research reactor LVR-15. The loops insertion in the reactor LVR-15 requires performing additional safety analyses studying the mutual interference of the loops and the reactor, especially in conditions of abnormal operation or accident conditions of the loops. The paper will provide examples of these analyses made using codes ATHLET (supercritical water) and TRACE (high temperature He) illustrating process of their assessment and practical use. These activities provide significant opportunity for TSO team in building its new competencies. Revised version of a paper presented at the Eurosafe, Paris, France, 6 and 7 November 2017. OPERATION AND NEW BUILD 221 1 Introduction The Centrum Výzkumu Řež (CVŘ) and its partners in the Czech Republic and abroad are supporting the development [1] of the Generation IV and Fusion concepts as well as demonstrators of these technologies such as ALLEGRO, ALFRED, DEMO and others. For this reason, the CVŘ has had a large R&D program financed from SUStainable Energy (SUSEN) project and from its continuation Research 4 Sustenibility (R4S) [2]. The construction and the operation of the new SUSEN infrastructure was supported by the grant of the Ministry of Education, Youth and Sports as the part of state help for the large research infrastructure in the Czech Republic dedicated to the period 2011–2019. The SUSEN project consists of 4 programs: 1. Technological Experimental Circuits (TEO) 2. Structural and System Diagnostics (SSD) 3. Nuclear Fuel Cycle (NFC) 4. Material Research (MAT) Within this program, several facilities were designed and built in order to study and to address new challenges of such new technologies. In particular, the paper focuses on two new loops which are going to be inserted inside the LVR-15 research reactor existing in Řež. The LVR-15 is a light water tank-type research reactor in operation since 1957. It is placed in a stainless steel vessel under a shielding cover, has forced cooling, uses IRT-4M type fuel and an has an operational power level of 10 MWt. The reactor operations run in campaigns that usually last for 3 weeks, followed by an outage lasting for 10 to 14 days necessary for maintenance and fuel reloading. There can be also other campaigns which can operate for ‘short-time’ experiments. Some of the LVR-15 applications are in the field of material irradiation research and services, neutron physics, development and production of new radiopharmaceuticals [3]. The loops in concern are the High Temperature Helium Loop (HTHL) and the Super Critical Water Loop (SCWL) and their main scope are to analyse the cladding behaviour and structural materials under different pressure, temperature and coolant media conditions different from the standard Light Water Reactors (LWR) technology [2]. In order to get the regulatory permit for in-pile operation of these loops in LVR-15, CVŘ has to prepare an amendment to the Final Safety Analyses Report (FSAR) containing safety analyse of the loops under | | Fig. 1. CVR Facilities list. operational and accidental conditions. Aim of this paper is to present the methodology and the analyses done in support of this process, starting from code benchmarking/assessment and the methods adopted in preparing the safety case. 2 Facilities description The map of experimental facilities put into operation in 2016 and those under preparation to be finalized in 2017 is shown in Figure 1 in the technology – knowledge map. In particular, the SCWL and HTHL represent a pioneer and unique experimental facility for Gen. IV and Fusion. 2.1 SCWL The SCWL is going to be a part of a research facility dedicated to GIV technologies which will focus on obtaining data in several areas of the supercritical fields like: corrosion processes of construction materials in supercritical water, with influence of Operation and New Build Experimental and Analytical Tools for Safety Research of GEN IV Reactors ı G. Mazzini, M. Kyncl, Alis Musa and M. Ruscak
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