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A new strategy to simulate a random geometry in a pebble-bed core with the Monte Carlo code MCNP

Title
A new strategy to simulate a random geometry in a pebble-bed core with the Monte Carlo code MCNP
Author
김종경
Keywords
Monte Carlo; MCNP; Pebble-bed; Random geometry
Issue Date
2011-06
Publisher
Elsevier Science B.V., Amsterdam.
Citation
Annals of Nuclear Energy, 2011, 38(9), p.1877-1883
Abstract
MCNP (TM) is one of the most widely used codes and is suitable for the validation of a new computer code for pebble-bed core analysis which will be developed in the future. In a pebble-bed core not only the fuel and moderator pebbles are randomly packed, but also the fuel-to-moderator pebble ratio is irregular. It is quite difficult to directly apply these features in MCNP (TM) simulations. A new method, that can efficiently simulate the characteristics of the pebble-bed core by using the MCNP (TM) code, was developed in this study. The key idea of the method is that the material composing the unit cell expanded by repeated-geometry feature of the code is randomly determined and the continuity of material is conserved. This method was validated by the benchmark problems for the pebble-bed cores. If this method is implemented into the MCNP (TM) code, greater variety of analyses for the pebble-bed core can be possible. (C) 2011 Elsevier Ltd. All rights reserved.
URI
https://www.sciencedirect.com/science/article/pii/S0306454911002015http://hdl.handle.net/20.500.11754/68007
ISSN
0306-4549
DOI
10.1016/j.anucene.2011.05.012
Appears in Collections:
COLLEGE OF ENGINEERING[S](공과대학) > NUCLEAR ENGINEERING(원자력공학과) > Articles
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