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

Carver, Michael; Tahir, A.; Kiteley, J.C.; Banaś, Aleksander; Rowe, D.S.; Midvidy, W. I.

doi:10.1016/0029-5493(90)90224-l

Cited by 14 publications

(2 citation statements)

References 6 publications

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“…ASSERT-PV [11][12][13] is based on ASSERT-IV [14], which in turn originated from the COBRA IV computer program; ASSERT-PV has been enhanced to meet the specific requirements for the thermalhydraulic analysis of 2-phase flow in the horizontally oriented PHWR fuel channels. The ASSERT-PV version for SCWR analysis is V3R1m2 developed to model flow and heat transfer in subchannels of fuel bundles under supercritical pressure conditions [15].…”

Section: Assert-pv Subchannel Codementioning

confidence: 99%

Evolution of the Canadian SCWR Fuel-Assembly Concept and Assessment of the 64 Element Assembly for Thermalhydraulic Performance

Dominguez¹,

Onder²,

Rao³

et al. 2016

CNL Nuclear Review

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Section: Assert-pv Subchannel Codementioning

confidence: 99%

Evolution of the Canadian SCWR Fuel-Assembly Concept and Assessment of the 64 Element Assembly for Thermalhydraulic Performance

Dominguez¹,

Onder²,

Rao³

et al. 2016

CNL Nuclear Review

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“…For example, both static and dynamic coupling can handle only slow transients in subchannels in a "quasi-steadystate" way unless the restart capability issue in ASSERT-PV is resolved. In contrast, a new advanced CATHENA code Tahir (as given by Carver [37])…”

Section: Summary and Recommendationmentioning

confidence: 99%

Strategies for Developing Subchannel Capability in an Advanced System Thermalhydraulic Code: A Literature Review

Cheng

Rao

2015

AECL Nuclear Review

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In the framework of developing next generation safety analysis tools, Canadian Nuclear Laboratories (CNL) has planned to incorporate subchannel analysis capability into its advanced system thermalhydraulic code CATHENA 4. This paper provides a literature review and an assessment of current subchannel codes. It also evaluates three code-development methods: (i) static coupling of CATHENA 4 with the subchannel code ASSERT-PV, (ii) dynamic coupling of the two codes, and (iii) fully implicit implementation for a new, standalone CATHENA 4 version with subchannel capability. Results of the review and assessment suggest that the current ASSERT-PV modules can be used as the base for the fully implicit implementation of subchannel capability in CATHENA 4, and that this option may be the most cost-effective in the long run, resulting in savings in user application and maintenance costs. In addition, improved versatility of the tool could be accomplished by the addition of new features that could be added as part of its development. The new features would improve the capabilities of the existing subchannel code in handling low, reverse, and stagnant flows often encountered in system thermalhydraulic analysis. Therefore, the method of fully implicit implementation is preliminarily recommended for further exploration. A feasibility study will be performed in an attempt to extend the present work into a preliminary development plan.

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The analysis of two-dimensional two-phase flow in horizontal heated tube bundles using drift flux model

Yang

Zheng

Wang

1999

Heat and Mass Transfer

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

Cited by 14 publications

References 6 publications

Evolution of the Canadian SCWR Fuel-Assembly Concept and Assessment of the 64 Element Assembly for Thermalhydraulic Performance

Evolution of the Canadian SCWR Fuel-Assembly Concept and Assessment of the 64 Element Assembly for Thermalhydraulic Performance

Strategies for Developing Subchannel Capability in an Advanced System Thermalhydraulic Code: A Literature Review

The analysis of two-dimensional two-phase flow in horizontal heated tube bundles using drift flux model

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