Prediction of departure from nucleate boiling in PWR fast power transients

An assessment is conducted of the differences in predicted results between use of steady state versus transient Departure from Nucleate Boiling (DNB) models, for fast power transients under forced convective heat exchange conditions. Theoretical DNB models based on liquid film thickness variation are adapted and modified from existing studies into a generalized formulation to allow implementation into a reactor simulation code. The formulation is validated using experimental data available at low pressure. An application is performed at Pressurized Water Reactor (PWR) operating conditions, simulating rod ejection accidents. The transient DNB model is applied to PWR rod ejection accident cases computed by the reactor dynamics code SIMULATE-3K. Rod power profiles deriving from pin power reconstruction are used in a subchannel simulation done with VIPRE to obtain local pin parameters. Results show that a significant delay exists for the occurrence of transient DNB compared to quasi steady-state DNB and in some cases DNB does not occur, even if predicted by quasi steady-state methods. Most modem codes for PWR thermal hydraulic simulation use quasi steady-state approaches to predict DNB, thus applying a steady-state correlation to time-dependent cases. However, according to the transient DNB model used in this work, a time lag exists between DNB as predicted by steady-state correlations, and effective transient DNB. During that time lag, the liquid film between the wall and the bubbly layer thins until the heated surface is eventually dried out. Such DNB prediction by steady state models is a conservative estimate. This work assesses the consequences of the use of more accurate models for predicting transient DNB, which are desirable to get better knowledge of design margins, to allow optimization of plant safety and efficiency.

Department dc:contributor.department

Massachusetts Institute of Technology. Department of Nuclear Science and Engineering.

Grantor dc:publisher

Massachusetts Institute of Technology

Year dc:date.issued

2013

Author dc:creator

• Lenci, Giancarlo

Advisor dc:contributor.advisor

• Kord S. Smith and Neil E. Todreas.

• Nuclear Science and Engineering.

Statement dc:rights

• M.I.T. theses are protected by copyright. They may be viewed from this source for any purpose, but reproduction or distribution in any format is prohibited without written permission. See provided URL for inquiries about permission.

Licence dc:rights.uri

• http://dspace.mit.edu/handle/1721.1/7582

Language dc:language.iso

eng

Handle dc:identifier.uri

http://hdl.handle.net/1721.1/80659

OAI identifier oai:identifier

oai:dspace.mit.edu:1721.1/80659