Simulation of standard temperature control indications at the outlet of a fuel assembly of VVER1000 reactor of Rostov NPP unit No. 2
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D. A. Oleksyuk
Abstract
In 2016 OECD put forward a routine problem to simulate the operation conditions in VVER-1000 reactor of Rostov NPP unit No. 2 taking into account control rod motions. The participants were encouraged to simulate the integrated process and obtain the indications of the hot leg temperature control sensors depending on control rod motions. The data from in the experiment at 75% nominal power was selected for the first test carried out in the frames of the international task. Insertion of the 10th and 9th CPS rod groups into the core without driving was carried out in the low power testing experiments at Rostov NPP unit No. 2 (May 31, 2010). The task was split into several subtasks, each with its own specifics. One of such subtasks is focused on the simulation of the standard temperature control indications at the FA outlet. The way of solving the abovementioned subtask is reflected in the present report.
Kurzfassung
Im Jahr 2016 stellte die OECD ein Benchmark zur Simulation der Betriebsbedingungen im VVER-1000-Reaktor des Rostower Kernkraftwerks Nr. 2 unter Berücksichtigung der Steuerstabbewegungen vor. Die Teilnehmer wurden ermutigt, den integrierten Prozess zu berechnen und die Werte der Temperaturfühler in Abhängigkeit von den Bewegungen des Steuerstabes zu bestimmen. Die Daten aus dem Experiment bei 75% Nennleistung wurden für den ersten Test im Rahmen der internationalen Aufgabe ausgewählt. Das Einbringen der 10. und 9. CPS-Stabgruppe in den Kern ohne Vortrieb erfolgte in den Low-Power-Testversuchen am Kernkraftwerk Rostov Nr. 2 (31. Mai 2010). Die Aufgabe wurde in mehrere Teilaufgaben mit jeweils eigenen Besonderheiten aufgeteilt. Eine dieser Teilaufgaben konzentriert sich auf die Simulation der Standard-Temperaturkontrollanzeigen am FA-Ausgang. Die Art und Weise der Lösung der oben genannten Teilaufgabe spiegelt sich im vorliegenden Bericht wider.
References
1 Nikonov, S.; Pasichnyk, I.; Velkov, K.: Hybrid thermo-hydraulic description of the VVER-1000 core using system code ATHLET. VNIIAES, Moscow, Russia. GRS mbH, Garching, Germany, 25th Symposium of AER October 13–16, 2015Suche in Google Scholar
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© 2018, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Editorial
- Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2017
- Technical Contributions/Fachbeiträge
- SIMULATE5-HEX extension for VVER analyses
- Application of discontinuity factors and group constants generated by SERPENT in the KIKO3 DMG code
- “Full-Core” VVER-440 extended calculation benchmark
- Calculation of “full core” VVER-1000 benchmark
- Study of neutron-physical characteristics of VVER-1200 considering feedbacks using MCU Monte Carlo code
- Advantages of VVER-440 fuel cycles with new fuel assemblies
- A neutronics feasibility study on utilization of a thinned cladding fuel design at Loviisa NPP
- Investigation of fuel cycles containing Generation IV reactors and VVER-1200 reactors
- Calculations of spent fuel isotopic composition for fuel rod from VVER-440 fuel assembly benchmark using several evaluated nuclear data libraries
- Simulation of standard temperature control indications at the outlet of a fuel assembly of VVER1000 reactor of Rostov NPP unit No. 2
- Power transient calculations with VERONA
- Physical startup tests calculations for Dukovany NPP using MOBY-DICK macrocode
- Renewing the refueling neutron monitoring and reactivity measurement systems at Paks NPP
- Hot channel calculation methodologies in case of VVER-1000/1200 reactors
- Contribution to the validation of the VVER-1000 Temelin NPP computing model for the ATHLET/DYN3D coupled codes
- Simulation of a hypothetical MSLB core transient in VVER-1000 with several stuck rods
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Editorial
- Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2017
- Technical Contributions/Fachbeiträge
- SIMULATE5-HEX extension for VVER analyses
- Application of discontinuity factors and group constants generated by SERPENT in the KIKO3 DMG code
- “Full-Core” VVER-440 extended calculation benchmark
- Calculation of “full core” VVER-1000 benchmark
- Study of neutron-physical characteristics of VVER-1200 considering feedbacks using MCU Monte Carlo code
- Advantages of VVER-440 fuel cycles with new fuel assemblies
- A neutronics feasibility study on utilization of a thinned cladding fuel design at Loviisa NPP
- Investigation of fuel cycles containing Generation IV reactors and VVER-1200 reactors
- Calculations of spent fuel isotopic composition for fuel rod from VVER-440 fuel assembly benchmark using several evaluated nuclear data libraries
- Simulation of standard temperature control indications at the outlet of a fuel assembly of VVER1000 reactor of Rostov NPP unit No. 2
- Power transient calculations with VERONA
- Physical startup tests calculations for Dukovany NPP using MOBY-DICK macrocode
- Renewing the refueling neutron monitoring and reactivity measurement systems at Paks NPP
- Hot channel calculation methodologies in case of VVER-1000/1200 reactors
- Contribution to the validation of the VVER-1000 Temelin NPP computing model for the ATHLET/DYN3D coupled codes
- Simulation of a hypothetical MSLB core transient in VVER-1000 with several stuck rods
