Validation of the Assert Subchannel Code: Prediction of Critical Heat Flux in Standard and Nonstandard Candu Bundle Geometries-Reference-Cited by-同舟云学术

Validation of the Assert Subchannel Code: Prediction of Critical Heat Flux in Standard and Nonstandard Candu Bundle Geometries

Published:1995-12 Issue:3 Volume:112 Page:299-314
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Carver M. B.¹,Kiteley J. C.¹,Zhou R. Q.-N.¹,Junop S. V.¹,Rowe D. S.²

Affiliation:

1. AECL Research, Chalk River Laboratories, Advanced Reactor Development Division Thermalhydraulics Development Branch, Chalk River, Ontario KOJI JO, Canada

2. Rowe & Associates, Redmond, Washington 98503

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/NT95-A35156

Reference19 articles.

1. J. C. KITELEY, M. B. CARVER, D. S. ROWE, and J. F. WASILEWICZ, “ASSERT (Version 2) User’s Manual,” COG proprietary report, CANDU Owners Group (1991).

2. Simulation of the distribution of flow and phases in vertical and horizontal bundles using the ASSERT-4 subchannel code

3. J. C. KITELEY, M. B. CARVER, and G. L. FESTARINI, “ASSERT-PV Assessment and Comparisons with ASSERT-IV,” COG Proprietary Report, CANDU Owners Group (1989).

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