Development of a parallel processing couple for calculations of control rod worth in terms of burn-up in a WWER-1000 reactor
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O. Noori-Kalkhoran
Abstract
In this study a code based method has been developed for calculation of integral and differential control rod worth in terms of burn-up for a WWER-1000 reactor. Parallel processing of WIMSD-5B, PARCS V2.7 and COBRA-EN has been used for this purpose. WIMSD-5B has been used for cell calculation and handling burn-up of core at different days. PARCS V2.7 has been used for neutronic calculation of core and critical boron concentration search. Thermal-hydraulic calculation has been performed by COBRA-EN. A Parallel processing algorithm has been developed by MATLAB to couple and transfer suitable data between these codes in each step. Steady-State Power Picking Factors (PPFs) of the core and Control rod worth have been calculated from Beginning Of Cycle (BOC) to 289.7 Effective full Power Days (EFPDs) in some steps. Results have been compared with Bushehr Nuclear Power Plant (BNPP) Final Safety Analysis Report (FSAR) results. The results show great similarity and confirm the ability of developed coupling in calculation of control rod worth in terms of burn-up.
Kurzfassung
In dieser Studie wurde auf der Basis von Rechencodes eine Methode zur Berechnung der integralen und differentiellen Kennwerte von Steuerstäben bezüglich des Abbrands in einem WWER-1000-Reaktor entwickelt. Dazu wurde die parallele Weiterverarbeitung von WIMSD-5B, PARCS V2.7 und COBRA-EN-Rechencodes verwendet. Der WIMSD-5B-Code wurde für die Zellberechnung und die Behandlung des Abbrands des Kerns verwendet, der PARCS V2.7-Code für die Neutronenberechnung, der COBRA-EN-Code für die thermohydraulischen Berechnungen. Ein paralleler Verarbeitungsalgorithmus wurde von MATLAB zur Kopplung und zum Transfer von geeigneten Daten zwischen diesen Codes verwendet. Die Ergebnisse wurden verglichen mit den Ergebnissen des Final Safety Analysis Reports (FSAR) des Bushehr-Kernkraftwerks (BNPP). Es zeigt sich eine große Ähnlichkeit der Ergebnisse was die Leistungsfähigkeit der entwickelten Methode zur Berechnung der Kennwerte von Steuerstäben bezüglich des Abbrands zeigt.
References
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© 2017, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- CANDU pressure tube leak detection by annulus gas dew point measurement: a critical review
- Multiple regression approach to predict turbine-generator output for Chinshan nuclear power plant
- 10.3139/124.110675
- Development of a parallel processing couple for calculations of control rod worth in terms of burn-up in a WWER-1000 reactor
- Simulation of protected and unprotected loss of flow transients in a WWER-1000 reactor based on the Drift-Flux Model
- Sensitivity analysis for CORSOR models simulating fission product release in LOFT-LP-FP-2 severe accident experiment
- Analysis of the optimal fuel composition for the Indonesian experimental power reactor
- Radiogenic lead from poly-metallic thorium ores as a valuable material for advanced nuclear facilities
- The effects of applying silicon carbide coating on core reactivity of pebble-bed HTR in water ingress accident
- Font Attributes based Text Steganographic algorithm (FATS) for communicating images: A nuclear power plant perspective
- Size control synthesis and characterization of ZnO nanoparticles and its application as ZnO-water based nanofluid in heat transfer enhancement in light water nuclear reactor
- Nuclear characteristics of epoxy resin as a space environment neutron shielding
- Exact solution of the neutron transport equation in spherical geometry
- Technical Notes/Technische Mitteilungen
- Determination of self-attenuation correction factor for lichen samples by using gamma-ray spectrometry
