Published 2006 | Version v1
Miscellaneous Open

Calculation of power density with MCNP in TRIGA reactor

  • 1. Inst. Jozef Stefan, Ljubljana (Slovenia)

Description

Modern Monte Carlo codes (e.g. MCNP) allow calculation of power density distribution in 3-D geometry assuming detailed geometry without unit-cell homogenization. To normalize MCNP calculation by the steady-state thermal power of a reactor, one must use appropriate scaling factors. The description of the scaling factors is not adequately described in the MCNP manual and requires detailed knowledge of the code model. As the application of MCNP for power density calculation in TRIGA reactors has not been reported in open literature, the procedure of calculating power density with MCNP and its normalization to the power level of a reactor is described in the paper. (author)

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Additional details

Publishing Information

Publisher
Nuclear Society of Slovenia
Imprint Place
Ljubljana (Slovenia)
ISBN
961-6207-26-3
Imprint Title
Proceedings of the International Conference Nuclear Energy for New Europe 2006
Imprint Pagination
vp.
Journal Page Range
[6 p.]
Report number
INIS-SI--07-002

Conference

Title
International Conference Nuclear Energy for New Europe 2006
Dates
18-21 Sep 2006
Place
Portoroz (Slovenia)

Optional Information

Lead record
8ame6-ve151
Notes
2 refs., 1 fig. Imprint:756 refs., 109 tabs., 481 figs.