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      System code improvements for modelling passive safety systems and their validation Translated title: Erweiterungen von Systemcodes zur Modellierung passiver Sicherheitssysteme und ihre Validierung

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      Kerntechnik
      Carl Hanser Verlag

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          Abstract

          GRS has been developing the system code ATHLET over many years. Because ATHLET, among other codes, is widely used in nuclear licensing and supervisory procedures, it has to represent the current state of science and technology. New reactor concepts such as Generation III+ and IV reactors and SMR are using passive safety systems intensively. The simulation of passive safety systems with the GRS system code ATHLET is still a big challenge, because of non-defined operation points and self-setting operation conditions. Additionally, the driving forces of passive safety systems are smaller and uncertainties of parameters have a larger impact than for active systems. This paper addresses the code validation and qualification work of ATHLET on the example of slightly inclined horizontal heat exchangers, which are e. g. used as emergency condensers (e. g. in the KERENA and the CAREM) or as heat exchanger in the passive auxiliary feed water systems (PAFS) of the APR+.

          Kurzfassung

          Der Systemcode ATHLET wird seit vielen Jahren von der GRS entwickelt. Da ATHLET, wie auch andere Codes, in Aufsichts- und Genehmigungsverfahren eingesetzt wird, muss es dem aktuellen Stand von Wissenschaft und Technik genügen. Passive Sicherheitssysteme werden von neuen Reaktorkonzepten wie Generation III+ und IV Reaktoren sowie SMR verstärkt genutzt. Die Simulation solcher passiven Systeme mit dem GRS-Code ATHLET ist noch immer eine große Herausforderung, da sie keine fest definierten Arbeitspunkte besitzen. Zusätzlich sind ihre treibenden Kräfte kleiner und Unsicherheiten in ihnen fallen hier stärker ins Gewicht. Dieses Paper beschreibt Validierungs- und Qualifikationsarbeiten der GRS für den Systemcode ATHLET am Beispiel von Wärmeübertragern mit leicht geneigten horizontalen Rohren, wie sie z. B. als Notkondensatoren (z. B. im KERENA oder CAREM) oder als Wärmeübertrager für ein passives Hilfsspeisewassersystem (PAFS) im APR+ eingesetzt werden sollen.

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          The Integral Test Facility Karlstein

          The Integral Test Facility Karlstein (INKA) test facility was designed and erected to test the performance of the passive safety systems of KERENA, the new AREVA Boiling Water Reactor design. The experimental program included single component/system tests of the Emergency Condenser, the Containment Cooling Condenser and the Passive Core Flooding System. Integral system tests, including also the Passive Pressure Pulse Transmitter, will be performed to simulate transients and Loss of Coolant Accident scenarios at the test facility. The INKA test facility represents the KERENA Containment with a volume scaling of 1 : 24. Component heights and levels are in full scale. The reactor pressure vessel is simulated by the accumulator vessel of the large valve test facility of Karlstein—a vessel with a design pressure of 11 MPa and a storage capacity of 125 m 3 . The vessel is fed by a benson boiler with a maximum power supply of 22 MW. The INKA multi compartment pressure suppression Containment meets the requirements of modern and existing BWR designs. As a result of the large power supply at the facility, INKA is capable of simulating various accident scenarios, including a full train of passive systems, starting with the initiating event—for example pipe rupture.
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            Passive BWR Integral LOCA Testing at the Karlstein Test Facility INKA

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              Author and article information

              Journal
              kt
              Kerntechnik
              Carl Hanser Verlag
              0932-3902
              2195-8580
              28 October 2016
              : 81
              : 5
              : 535-542
              Affiliations
              1 Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Forschungszentrum, Boltzmannstraße 14, 85748 Garching
              Author notes
              Article
              KT110720
              10.3139/124.110720
              0bbcd1bf-1d6d-42cd-bea1-3dac14676a27
              © 2016, Carl Hanser Verlag, München
              History
              : 21 February 2016
              Page count
              References: 14, Pages: 8
              Categories
              Technical Contributions/Fachbeiträge

              Materials technology,Materials for energy,Nuclear physics
              Materials technology, Materials for energy, Nuclear physics

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