The DOI matches its Crossref record.
A New CHF Correlation Scheme Proposed for Vertical Rectangular Channels Heated From Both Sides in Nuclear Research Reactors
Abstract
In this study, an investigation was carried out to identify the important parameters affecting critical heat flux (CHF) in rectangular channels, focusing on the effects of flow direction, channel inlet subcooling from 1 to 213 K, the channel outlet condition extending from subcooling of 0–74 K to quality of 0–1.0, pressure of 0.1 to 4 MPa, water mass flux of −25,800 to + 6250 kg/m2s, and channel configuration. In particular, the effect of the outlet subcooling in upflow and downflow on the CHF was quantitatively investigated. As a result of this study, a new CHF scheme covering downflow, countercurrent flow, and upflow was established in the rectangular channels within the ranges of parameters investigated in this study.
Overview
Integrity signals
Registry
Cites
Statistics
Verification
Claims the paper makes
Claims other papers make about this one
Each is checked against this paper’s own text: does it say what the citing paper says it does?
In the citing paper
“One of the experimental conditions was channel inlet subcooling which was 1 K to 74 K (Sudo, 1993).”
From Conversion Preliminary Safety Analysis Report for the NIST Research Reactor (2015) · cites this paper as Sudo, 1993
Citations
Cited by
Sorted by citations
Conversion Preliminary Safety Analysis Report for the NIST Research Reactor
Brookhaven National Laboratory (BNL), U., Diamond, D., (NNSA), U. N. N. S. A., Baek, J., Hanson, A., Cheng, L.-Y., Brown, N., & Cuadra, A. (2015) · doi:10.2172/1169032 · Cited by 12
Metadata
- Authors
- Sudo, Y., & Kaminaga, M.
- Affiliations
- Japan Atomic Energy Agency (JP)
- ORCID
- Sudo, Y.
- Venue
- Journal of Heat Transfer
- Publisher
- Wiley
- Published
- 1993-05-01
- Volume
- 115
- Issue
- 2
- Pages
- 426-434
- ISSN
- 0022-1481 (ISSN-L)
- 1528-8943
- OpenAlex
- W1993480566
- Cited by
- 92
- References
- 0
- Citations by year
- 2026: 6 · 2025: 9 · 2024: 12 · 2023: 4 · 2022: 4 · 2021: 5 · 2020: 5 · 2019: 3 · 2018: 2 · 2017: 3 · 2016: 1 · 2015: 3 · 2014: 2 · 2013: 4 · 2012: 4
- FWCI
- 4.40
- Type
- journal article
- Language
- en
- Open access
- closed
- Locations
- ASME Journal of Heat and Mass Transfer (publishedVersion)
- Topics
- Physical Sciences › Engineering › Mechanical Engineering › Heat Transfer and Boiling Studies
- Physical Sciences › Energy › Nuclear Energy and Engineering › Nuclear Engineering Thermal-Hydraulics
- Physical Sciences › Engineering › Computational Mechanics › Heat transfer and supercritical fluids
- Keywords
- critical heat flux, CHF correlation, vertical rectangular channel, research reactor, flow direction, countercurrent flow, upward flow, downflows, water mass flux, pressure effects, channel configuration
About these checks
Registry, retraction, Cites and statistics results are computed, not judged, with one exception: a printed reference that no index lists is read once by a model before it counts as a citation error. Claims are extracted by a model and kept only when their quote appears verbatim in the text; each cited source is then checked, with a model’s help, for whether it says what the claim relies on. Those verdicts can be wrong — read the claim’s quote and the cited source before relying on one.
Statistics and arithmetic are recomputed, not judged.
Confidence bands are shown only for fields calibrated on our annotated test set. None is calibrated yet, so no band is shown.
What counts as a claim ›How we measure confidence ›How we check this ›
Are you an author, or do you see a problem with this page? Request a review
