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  4. Within-pin 238U-capture distributions: CASMO-4 and MCNP vs. activation foil measurements
 
research article

Within-pin 238U-capture distributions: CASMO-4 and MCNP vs. activation foil measurements

Macku, K.
•
Jatuff, F.
•
Murphy, M.
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2005
Transactions of the American Nuclear Society

The design of modern BWR assemblies is governed by general requirements such as safe and reliable performance, optimal fuel utilization and cycle length, and a high degree of flexibility in reactor operation. These requirements are fulfilled via the use of increased enrichments, high gadolinium loadings and part-length fuel rods, which lead to very heterogeneous assembly designs, causing not only large variations in the power density of individual fuel pins, but also strong radial and azimuthal gradients in reaction rate distributions within the pins themselves. The invasive technique of activation foils (depleted uranium) is applied and the experimental results are compared with calculations performed using the deterministic code CASMO-4 as well as the stochastic code MCNP

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Type
research article
Author(s)
Macku, K.
Jatuff, F.
Murphy, M.
Grimm, P.
Joneja, O. P.
Chawla, R.  
Date Issued

2005

Publisher

ANS

Published in
Transactions of the American Nuclear Society
Volume

93

Start page

667

End page

8

Subjects

fission reactor design

•

fission reactor fuel

•

fission reactor physics

•

fission reactor safety

•

fission reactor theory

•

Monte Carlo methods

•

nuclear engineering computing

Note

Lab. for Reactor Phys. Syst. Behaviour, Paul Scherrer Inst., Villigen, Switzerland

Editorial or Peer reviewed

REVIEWED

Written at

EPFL

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Available on Infoscience
September 17, 2010
Use this identifier to reference this record
https://infoscience.epfl.ch/handle/20.500.14299/53861
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