2019 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.

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

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
UN Sustainable Development Goal Categories
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
UN Sustainable Development Goal Categories
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

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

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)
UN Sustainable Development Goal Categories
Source: Web Of Science
Added: August 6, 2018

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