Published August 1997 | Version v1
Journal article

Code PULSAR+ verification

  • 1. Inst. Reaktornykh Tekhnologij i Materialov RNTh Kurchatovskij Inst., Moscow (Russian Federation)

Description

Examples of the PULSAR+ code verification simulating fuel can behaviour during accidents at NPPs are given. The results of experiments and those of simulation dealing with oxidation, tightness loss and local deformation of the fuel cans are compared. It is shown that the program block simulating oxidation of zirconium cans during their interaction with steam at temperatures of 800-1000 deg C adequately describes the temperature dependence of the oxidation rate. The conclusion on high reliability of the applied criteria of fuel can failure under simultaneous effects of creep and plasticity is made. The deformation pattern for one fuel element cluster at fast temperature increase and coolant pressure decrease is considered as an example of the PULSAR+ code application for simulation of the WWER-1000 reactor fuel assembly behaviour

Additional details

Additional titles

Original title (Russian)
Верификация программного комплекса PULSAR+

Publishing Information

Journal Title
Atomnaya Ehnergiya
Journal Volume
83
Journal Issue
2
Journal Page Range
p. 120-124
ISSN
0004-7163

Optional Information

Notes
4 refs., 4 figs., 4 tabs.