skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: CTF Void Drift Validation Study

Technical Report ·
DOI:https://doi.org/10.2172/1342656· OSTI ID:1342656
 [1];  [2];  [1];  [2]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Pennsylvania State Univ., University Park, PA (United States)

This milestone report is a summary of work performed in support of expansion of the validation and verification (V&V) matrix for the thermal-hydraulic subchannel code, CTF. The focus of this study is on validating the void drift modeling capabilities of CTF and verifying the supporting models that impact the void drift phenomenon. CTF uses a simple turbulent-diffusion approximation to model lateral cross-flow due to turbulent mixing and void drift. The void drift component of the model is based on the Lahey and Moody model. The models are a function of two-phase mass, momentum, and energy distribution in the system; therefore, it is necessary to correctly model the ow distribution in rod bundle geometry as a first step to correctly calculating the void distribution due to void drift.

Research Organization:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Consortium for Advanced Simulation of LWRs (CASL)
Sponsoring Organization:
USDOE
DOE Contract Number:
AC05-00OR22725
OSTI ID:
1342656
Report Number(s):
ORNL/TM-2015/641; NT0304000; NEAF343; ORNL/SR-2015/641
Country of Publication:
United States
Language:
English

Similar Records

Two-Phase Void Drift Phenomena in a 2 x 3 Rod Bundle: Flow Redistribution Data and Their Analysis
Journal Article · Sat Oct 15 00:00:00 EDT 2005 · Nuclear Technology · OSTI ID:1342656

Validation and Benchmarking of CTF For Single- And Two-Phase Flow Using VIPRE-01
Conference · Fri Sep 01 00:00:00 EDT 2017 · OSTI ID:1342656

Assessment of the Subchannel Code CTF for Single- and Two-Phase Flows
Journal Article · Fri Sep 07 00:00:00 EDT 2018 · Nuclear Technology · OSTI ID:1342656

Related Subjects