Fast Reactors and Accelerator Driven Systems Knowledge Base
Conference Article: Development of GRIF-SM: The code for analysis of beyond design basis accidents in sodium cooled reactors
Chvetsov, I.; Kouznetsov, I.; Volkov, A. (State Scientific Center of Russian Federation, Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation))Abstract
GRIF-SM code was developed at the IPPE fast reactor department in 1992 for the analysis of transients in sodium cooled fast reactors under severe accident conditions. This code provides solution of transient hydrodynamics and heat transfer equations taking into account possibility of coolant boiling, fuel and steel melting, reactor kinetics and reactivity feedback due to variations of the core components temperature, density and dimensions. As a result of calculation, transient distribution of the coolant velocity and density was determined as well as temperatures of the fuel pins, reactor core and primary circuit as a whole. Development of the code during further 6 years period was aimed at the modification of the models describing thermal hydraulic characteristics of the reactor, and in particular in detailed description of the sodium boiling process. The GRIF-SM code was carefully validated against FZK experimental data on steady state sodium boiling in the electrically heated tube; transient sodium boiling in the 7-pin bundle; transient sodium boiling in the 37-pin bundle under flow redaction simulating ULOF accident. To show the code capabilities some results of code application for beyond design basis accident analysis on BN-800- type reactor are presented.
view the full text of this article (21 pages, format: PDF, size= 989kB)
key words: boiling; coolant loops; fuel element clusters; g codes; hydrodynamics; reactivity; reactor cores; risk assessment; sodium cooled reactors; sodium; temperature dependence; transients
- Reference:
- Technical committee meeting on methods and codes for calculations of thermohydraulic parameters for fuel, absorber pins and assemblies of LMFR's with traditional and burner cores. Obninsk (Russian Federation) 27-31 Jul 1998
- International Atomic Energy Agency, Vienna (Austria)
- IAEA-TECDOC--1157, pp:129-149
- International Atomic Energy Agency, Vienna (Austria)