2016 ◽  
Vol 182 (4) ◽  
pp. 395-416 ◽  
Author(s):  
Dimitar Altiparmakov ◽  
Robert Wiersma

2010 ◽  
Vol 73 (13) ◽  
pp. 2180-2187
Author(s):  
M. I. Gurevich ◽  
M. A. Kalugin ◽  
A. V. Pryanichinikov ◽  
O. V. Tel’kovskaya ◽  
D. A. Shkarovskii

2004 ◽  
Vol 45 (2-4) ◽  
pp. 119-124 ◽  
Author(s):  
Boyan D. Ivanov ◽  
Kostadin N. Ivanov ◽  
Rudi J.J. Stamm'ler

2021 ◽  
Vol 8 (4) ◽  
pp. 10-19
Author(s):  
Tiep Nguyen Huu ◽  
Dung Nguyen Thi ◽  
Phu Tran Viet ◽  
Thanh Tran Vinh ◽  
Ha Pham Nhu Viet

The present work aims to perform burnup calculation of the OECD VVER-1000 LEU (lowenriched uranium) computational benchmark assembly using the Monte Carlo code MCNP6 and the deterministic code SRAC2006. The new depletion capability of MCNP6 was applied in the burnup calculation of the VVER-1000 LEU benchmark assembly. The OTF (on-the-fly) methodology of MCNP6, which involves high precision fitting of Doppler broadened cross sections over a wide temperature range, was utilized to handle temperature variation for heavy isotopes. The collision probability method based PIJ module of SRAC2006 was also used in this burnup calculation. The reactivity of the fuel assembly, the isotopic concentrations and the shielding effect due to the presenceof the gadolinium isotopes were determined with burnup using MCNP6 and SRAC2006 incomparison with the available published benchmark data. This study is therefore expected to reveal the capabilities of MCNP6 and SRAC2006 in burnup calculation of VVER-1000 fuel assemblies.


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