Subchannel Analysis Program for Boiling Water Reactor Fuel Bundles Based on Five Conservation Equations of Two-Phase Flow-Reference-Cited by-同舟云学术

Subchannel Analysis Program for Boiling Water Reactor Fuel Bundles Based on Five Conservation Equations of Two-Phase Flow

Published:1985-05 Issue:2 Volume:69 Page:210-217
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Bessho Yasunori¹,Uchikawa Sadao¹

Affiliation:

1. Energy Research Laboratory, Hitachi, Ltd. 1168 Moriyama-cho, Hitachi-shi, Ibaraki-ken 316, 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/NT85-A33632

Reference14 articles.

1. Methods for Detailed Thermal and Hydraulic Analysis of Water-Cooled Reactors

2. Two-fluid model of two-phase flow in a pin bundle of a nuclear reactor

3. R. W. BOWRING, “HAMBO, A Computer Programme for the Subchannel Analysis of the Hydraulic and Burnout Characteristics of Rod Clusters, Pt. II, The Equations,” AEEW-R582, United Kingdom Atomic Energy Authority (Jan. 1968).

4. C. W. STEWART, C. A. McMONAGLE, M. J. THURGOOD, T. L. GEORGE, D. S. TRENT, J. M. CUTA and G. D. SEYBOLD, “Core Thermal Model: COBRA-IV Development and Applications,” BNWL-2212, Battelle-Pacific Northwest Laboratory (Jan. 1977).

5. Mass Flux and Enthalpy Distribution in a Rod Bundle for Single- and Two-Phase Flow Conditions

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4. PREDICTION OF TRANSIENT BOILING TRANSITION IN BWR FUEL-ROD BUNDLES BY SUBCHANNEL ANALYSIS PROGRAM MENUETT;J NUCL SCI TECHNOL;1988

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