@article{6155c52287614497b9b8812e986e9e34,
title = "Rod Bundle Heat Transfer Thermal-Hydraulic Program",
abstract = "The U.S. Nuclear Regulatory Commission has been conducting thermal-hydraulic research using the Rod Bundle Heat Transfer (RBHT) facility at the Pennsylvania State University since 2001. The facility has been used for five individual test programs: forced reflood, steam cooling, mixture level swell, dispersed droplet injection, and oscillatory reflood test series. While rod bundle thermal hydraulics has been extensively studied in the past, the RBHT data have provided new insights into rod bundle phenomena especially on the effects of spacer grids. This paper provides a summary of the RBHT test program and discusses some of the major findings from this research with the emphasis on reflood thermal hydraulics and the effect of spacer grids. Of particular interest are data that enable model and correlation development. Recent efforts have focused on the evaluation of RBHT data and development of improved models and correlations suitable for systems thermal-hydraulic codes such as TRACE and RELAP. Because of detailed instrumentation on and about spacer grids, RBHT data have enabled improved models for convective heat transfer enhancement and droplet breakup. New correlations for the inverted annular and the inverted slug film boiling regimes have also been developed as an initial step toward an improved model for dispersed droplet film boiling.",
author = "Bajorek, {Stephen M.} and Cheung, {Fan Bill}",
note = "Funding Information: The work at the RBHT facility is the result of an outstanding team of researchers{\textquoteright} efforts since its inception and the construction and operation of the facility, conducting of the tests, and evaluation of the data have been a collaborative effort. Credit for the results reported in this paper is shared among many. The work of Brian Lowery, Molly Hanson, and previously by Ralph Rosal are greatly appreciated. The design, construction, and safe operation of a facility involving high power and high temperatures are unique skills and have been vital to the project. Our colleagues at the NRC have been endlessly supportive and the expert project management of Kirk Tien and untiring assistance by Chris Hoxie is greatly appreciated. A considerable number of graduate students from the Pennsylvania State University have assisted in the efforts. Evaluation of the data has been performed by numerous talented individuals including F. R. Beck, S. Ebrahim, S. Ergun, C. Frepoli, V. D. Fudurich, M. Holowach, A. Ireland, Y. Jin, H. Kumru, D. Miller, L. Mohanta, S. Qiao, A. Rau, M. Riley, F. A. Sohag, J. P. Spring, S. G. Srinivasan, and D. Todd. Many have gone on to productive careers in the nuclear industry. The authors are most indebted to our friend and mentor, Larry Hochreiter, a true pioneer and expert in the field of nuclear thermal hydraulics. The innovative features in RBHT and the facility itself were to due Larry{\textquoteright}s dedication to nuclear safety, technology development, and many years of experience in reflood heat transfer. His knowledge and friendship has benefitted many in this field of study. Publisher Copyright: {\textcopyright} 2019, {\textcopyright} 2019 American Nuclear Society.",
year = "2019",
month = jan,
day = "2",
doi = "10.1080/00295450.2018.1510697",
language = "English (US)",
volume = "205",
pages = "307--327",
journal = "Nuclear Technology",
issn = "0029-5450",
publisher = "Taylor and Francis Ltd.",
number = "1-2",
}