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  4. Comparisons of deterministic neutronic calculations with Monte Carlo results for an advanced BWR fuel assembly with hafnium control blades
 
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research article

Comparisons of deterministic neutronic calculations with Monte Carlo results for an advanced BWR fuel assembly with hafnium control blades

Plaschy, Michael
•
Jatuff, Fabian
•
Grimm, Peter
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2006
Journal of Nuclear Science and Technology

From the neutronic viewpoint, the optimization of BWR core designs is strongly related to the accurate determination of flux variations inside and around fuel assemblies. These fluctuations, which are mainly due to the high heterogeneity of the fuel and moderator regions, as additionally to the presence of cruciform absorber blades, have a direct impact on reactor safety and performance. Of particular importance is the pin power distribution, leading to the need of assessing the capabilities of design tools in a sufficiently rigorous manner. The basic configuration chosen for the code comparisons corresponds to a SVEA-96 fuel assembly under full-density water moderation conditions, with inserted hafnium absorber blades. The calculational schemes employed are the Monte Carlo code MCNPX2.5, in conjunction with various nuclear data libraries (ENDF/B-VI, JEF2.2, JEFF3.0, JENDL-3.2 and JENDL3.3), and the deterministic codes CASMO4 with JEF2.2, BOXER with JEF1.0 and HELIOS1.6 with ENDF/B-VI based libraries, respectively. The significant discrepancies observed in k, predictions (500pcm) are found to be mainly nuclear data related. On the other hand, data library effects have been found to be quite small for the prediction of pin-wise distributions of total fissions (Ftot), 238U captures (C8), as also of the C8/Ftot ratio. Significant differences in these reaction rate distributions (up to several percent) have, however, been observed between the Monte Carlo and deterministic calculations, particularly in the vicinity of the hafnium blades and in the gadolinium pins. Atomic Energy Society of Japan.

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Type
research article
DOI
10.3327/jnst.43.1298
Author(s)
Plaschy, Michael
•
Jatuff, Fabian
•
Grimm, Peter
•
Tani, Filippo
•
Jacot-Guillarmod, Roland
•
Giust, Flavio
•
Krouthen, Jan
•
Chawla, Rakesh  
Date Issued

2006

Publisher

Atomic Energy Society of Japan

Published in
Journal of Nuclear Science and Technology
Volume

43

Issue

11

Start page

1298

End page

1310

Subjects

Boiling water reactors

•

Accident prevention

•

Control rods

•

Data storage equipment

•

Digital libraries

•

Fluxes

•

Gadolinium

•

Hafnium

•

Moderators

•

Monte Carlo methods

•

Neutrons

•

Numerical methods

•

Optimization

•

Rate constants

Note

Paul Scherrer Institute, CH-5232 Villigen PSI, Switzerland

Peer reviewed

REVIEWED

Written at

EPFL

EPFL units
LRS  
Available on Infoscience
September 17, 2010
Use this identifier to reference this record
https://infoscience.epfl.ch/handle/20.500.14299/53883
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