Development and testing of three dimensional, two-fluid code THERMIT for LWR core and subchannel applications
At head of title: Energy Laboratory and Dept. of Nuclear Engineering.
Main Authors: | Kelly, John Edward, Kazimi, Mujid S. |
---|---|
Format: | Technical Report |
Language: | en_US |
Published: |
MIT Energy Laboratory
2006
|
Subjects: | |
Online Access: | http://hdl.handle.net/1721.1/35184 |
Similar Items
-
User's guide for THERMIT-2 : a version of THERMIT for both core-wide and subchannel analysis of light water reactors
by: Kelly, J. E., et al.
Published: (2011) -
THERMIT-2 : a two-fluid model for light water reactor subchannel transient analysis
by: Kelly, J. E., et al.
Published: (2011) -
Development of a three-dimensional two-fluid code with transient neutronic feedback for LWR applications
by: Griggs, D. P., et al.
Published: (2011) -
Development of models for the sodium version of the two-phase three dimensional thermal hydraulics code THERMIT
by: Wilson, Gregory James, et al.
Published: (2006) -
LWR core thermal-hydraulic analysis : assessment and comparison of the range of applicability of the codes COBRA IIIC/MIT and COBRA IV-I
by: Kelly, J. E., et al.
Published: (2006)