Aysenur Toptan

Works (5)

Updated: July 5th, 2023 15:34

2019 journal article

Gap conductance modeling I: Theoretical considerations for single- and multi-component gases in curvilinear coordinates

NUCLEAR ENGINEERING AND DESIGN, 353.

By: A. Toptan n, D. Kropaczek n & M. Avramova n

author keywords: Gap conductance; Temperature jump distance; Thermal accommodation coefficient; Static load; Mixture
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7. Affordable and Clean Energy (OpenAlex)
Source: Web Of Science
Added: October 21, 2019

2019 journal article

Gap conductance modeling II: Optimized model for UO2-Zircaloy interfaces

NUCLEAR ENGINEERING AND DESIGN, 355.

By: A. Toptan n, D. Kropaczek n & M. Avramova n

author keywords: Gap conductance; Continuum; Ross-Stoute; Nuclear fuel performance; Uncertainty; Doppler temperature
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6. Clean Water and Sanitation (OpenAlex)
Source: Web Of Science
Added: November 18, 2019

2019 journal article

On the validity of the dilute gas assumption for gap conductance calculations in nuclear fuel performance codes

NUCLEAR ENGINEERING AND DESIGN, 350, 1–8.

By: A. Toptan n, D. Kropaczek n & M. Avramova n

author keywords: Fill gas thermal conductivity; Gap conductance; Fuel performance; Doppler; Mixture thermal conductivity; Rod internal pressure; Dilute; Dense
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7. Affordable and Clean Energy (OpenAlex)
13. Climate Action (Web of Science)
Source: Web Of Science
Added: June 24, 2019

2018 journal article

A new fuel modeling capability, CTFFuel, with a case study on the fuel thermal conductivity degradation

NUCLEAR ENGINEERING AND DESIGN, 341, 248–258.

By: A. Toptan n, R. Salko *, M. Avramova n, K. Clarno* & D. Kropaczek n

author keywords: CTFFuel; Thermal conductivity degradation; CTF; SQA; Verification
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7. Affordable and Clean Energy (OpenAlex)
Source: Web Of Science
Added: December 31, 2018

2018 journal article

Implementation and assessment of wall friction models for LWR core analysis

ANNALS OF NUCLEAR ENERGY, 115, 565–572.

By: A. Toptan n, N. Porter n, R. Salko * & M. Avramova n

author keywords: Friction factor; CTF; Pressure drop; Subchannel analysis; Validation; Verification
TL;DR: The modeling of frictional pressure drop in the nuclear thermal hydraulics subchannel code, CTF, is improved through the addition of three new modeling options which allow the code to account for the effects of surface roughness and the third enables a user-supplied option. (via Semantic Scholar)
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Source: Web Of Science
Added: August 6, 2018

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