The Analyses of Measured Nuclide Concentration in Project ISTC 2670

V. ChrapĨiak / VUJE, Inc. / Slovakia

16th Symposium of AER on VVER Reactor Physics and Reactor Safety (2006, Bratislava, Slovakia)
Physical Problems of Spent Fuel Decommissioning and Radwaste


In this article are analyzed experiments for VVER-440 fuel and compared with theoretical results by new version of the SCALE 5 code:
nuclide compositions – measurement in Kurchatov institute for 3.6%
- measurement in Dimitrovgrad for 3.6% (project ISTC 2670)
The focus is on modules TRITON and ORIGEN-S.

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