Critical Power Correlation for Axially Uniformly Heated Tight-Lattice Bundles-Reference-Cited by-同舟云学术

Critical Power Correlation for Axially Uniformly Heated Tight-Lattice Bundles

Published:2003-07 Issue:1 Volume:143 Page:89-100
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Kureta Masatoshi¹,Akimoto Hajime¹

Affiliation:

1. Japan Atomic Energy Research Institute, Tokai Research Establishment Nuclear Energy System Department, Tokai-mura, Naka-gun, Ibaraki 319-1195, Japan

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT143-89

Reference10 articles.

1. B. W. LE TOURNEAU, A. C. PETERSON, K. J. COELING, M. E. GAVIN and S. J. GREEN, “Critical Heat Flux and Pressure Drop Tests with Parallel Upflow of High Pressure Water in Bundles of Twenty 0.25- and 0.28-Inch Diameter Rods,” WAPD-TM-1013, Bettis Atomic Power Laboratory (1975).

2. Critical Heat Flux and Pressure Drop Tests with Parallel Upflow of High Pressure Water in Bundles of Twenty ¾-in. Rods

Cited by 17 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. The thermal hydraulic phenomenon in tight lattice bundles: A review;Annals of Nuclear Energy;2019-04

2. Core Design and Analysis of Axially Heterogeneous Boiling Water Reactor for Burning Transuranium Elements;Nuclear Science and Engineering;2017-06-29

3. Critical Power and Void Fraction Prediction of Tight Bundle Designs;Nuclear Technology;2016-12

4. Thermal Feasibility Analyses for the 1356MWe High Conversion-Type Innovative Water Reactor for Flexible Fuel Cycle;Heat Transfer Engineering;2008-08

5. Effect of rod bowing on critical power based on tight-lattice 37-rod bundle experiments;J NUCL SCI TECHNOL;2008