PROCEEDINGS OF IBRAE RAS ISSUE 1: MODELS FOR THE FUEL ROD MATERIALS INTERACTIONS DURING REACTOR CORE DEGRADATION UNDER SEVER ACCIDENT CONDITIONS AT NPP (IN ENGLISH)

Ed. by L.A. Bolshov

A set of mechanistic models for the main degradation phenomena: cladding oxidation, hydrogen absorption and mechanical deformation, UO2 and ZrO2 dissolution by molten Zr, was developed in the Nuclear Safety Institute (IBRAE) RAS and combined in the code package SVECHA. In order to be applied to mechanistic modeling of various single-rod degradation experiments (including the FZK QUENCH tests), the models were tightly coupled in the advanced mechanistic code SVECHA/QUENCH. The models were also implemented in various system-level SA codes: ICARE2 (IRSN, France), SCDAP/RELAP5 (NRC, USA), the Russian SA codes RATEG/SVECHA and SOCRAT. The book presents the main models of the code package SVECHA and the single-rod code SVECHA/QUENCH.

Bibliographical reference

Models for the Fuel Rod Materials Interactions during Reactor Core Degradation under Sever Accident Conditions at NPP (in English). Edited by Professor V.F. Strizhov. — Proceedings of Nuclear Safety Institute RAS (IBRAE RAS). Edited by corresponding member of RAS L.A. Bolshov. Issue 1. — Moscow: Nauka, 2007. — 127 p.: illustrations.