Analysis of the Kalinin-3 coolant transient benchmark by SKETCH-N/SKAZKA code system

Author:

Ojinnaka Chukwudi A.S.,Zimin Vyacheslav G.,Strashnykh Vadim P.,Nikonov Sergei P.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference12 articles.

1. Coupling of COBAYA3/SUBCHANFLOW inside the NURESIM platform and validation using selected benchmarks;Calleja;Ann. Nucl. Energy,2014

2. Development of a Cross-Section Methodology and a Real-Time Core Model for VVER-1000 Simulator Application;Georgieva,2016

3. Simulation of the OECD NEA Kalinin-3 benchmark (phase 2) by the ATHLET-KIKO3D code system;Keresztúri,2012

4. Validation and verification of the coupled neutron kinetic/thermal hydraulic system code DYN3D/ATHLET;Kozmenkov;Ann. Nucl. Energy,2015

5. Makhin, I., Petkevich, I., Alekhin, G., Kurakin, K., Ustinov, A. and Bykov, M., (2010). Preliminary calculation results of the OECD/NEA Kalinin-3 coolant transient benchmark using the coupled thermohydraulic computer code packages TRAP-KS and KORSAR/GP (Exercise 2). Seminar on OECD Benchmark for Kalinin-3 Coupled Code Calculations and Uncertainty Analysis in Modelling. Hosted by the University of Pisa, Italy in April 12-13, 2010.

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