Home > Research > Publications & Outputs > Multiscale Approach of Investigating the Densit...

Links

Text available via DOI:

View graph of relations

Multiscale Approach of Investigating the Density of Simulated Fuel for a Zero Power Reactor

Research output: Contribution to Journal/MagazineJournal articlepeer-review

Published

Standard

Multiscale Approach of Investigating the Density of Simulated Fuel for a Zero Power Reactor. / Sardar, Suneela; Degueldre, Claude; Green, Sarah.
In: Journal of Nuclear Engineering, Vol. 5, No. 3, 20.09.2024, p. 420-435.

Research output: Contribution to Journal/MagazineJournal articlepeer-review

Harvard

APA

Vancouver

Sardar S, Degueldre C, Green S. Multiscale Approach of Investigating the Density of Simulated Fuel for a Zero Power Reactor. Journal of Nuclear Engineering. 2024 Sept 20;5(3):420-435. doi: 10.3390/jne5030026

Author

Bibtex

@article{066a68b633fc48f089920cd3f44e43c7,
title = "Multiscale Approach of Investigating the Density of Simulated Fuel for a Zero Power Reactor",
abstract = "With growing interest in molten salts as possible nuclear fuel systems, knowledge of thermophysical properties of complex salt mixtures, e.g., NaCl-CeCl3, NaCl-UCl3 and NaCl-UCl4, informs understanding and performance modelling of the zero power salt reactor. Fuel density is a key parameter that is examined in a multiscale approach in this paper. In the zero power reactor {\textquoteleft}core{\textquoteright} (cm level), the relative fuel density is estimated for the fuel pin disposition, as well as a function of their pitch (strong effect). Fuel density of the {\textquoteleft}pellet{\textquoteright} (mm–µm level) is first estimated on a geometrical basis, then through tracking pores and cracks using 2D (SEM) and 3D (laser microscopy, LM) techniques. For the nanoscale level, {\textquoteleft}grains{\textquoteright} analysis is done using X-ray diffraction (XRD), revealing the defects, vacancies and swelled grains. Initially, emphasis is on the near-eutectic composition of salt mixtures of CeCl3 with NaCl as the carrier salt. Cerium trichloride (CeCl3) is an inactive surrogate of UCl3 and PuCl3. The results were measured for the specific salt mixture (70 mol% NaCl and 30 mol% CeCl3) in this work, establishing that microscopy and XRD are important techniques for measurement of the physical properties of salts component pellets. This work is of significance, as densities of fuel components affect the power evolution through reactivity and the average neutronic behaviour in zero power salt reactors.",
author = "Suneela Sardar and Claude Degueldre and Sarah Green",
year = "2024",
month = sep,
day = "20",
doi = "10.3390/jne5030026",
language = "English",
volume = "5",
pages = "420--435",
journal = "Journal of Nuclear Engineering",
issn = "2673-4362",
publisher = "MDPI AG",
number = "3",

}

RIS

TY - JOUR

T1 - Multiscale Approach of Investigating the Density of Simulated Fuel for a Zero Power Reactor

AU - Sardar, Suneela

AU - Degueldre, Claude

AU - Green, Sarah

PY - 2024/9/20

Y1 - 2024/9/20

N2 - With growing interest in molten salts as possible nuclear fuel systems, knowledge of thermophysical properties of complex salt mixtures, e.g., NaCl-CeCl3, NaCl-UCl3 and NaCl-UCl4, informs understanding and performance modelling of the zero power salt reactor. Fuel density is a key parameter that is examined in a multiscale approach in this paper. In the zero power reactor ‘core’ (cm level), the relative fuel density is estimated for the fuel pin disposition, as well as a function of their pitch (strong effect). Fuel density of the ‘pellet’ (mm–µm level) is first estimated on a geometrical basis, then through tracking pores and cracks using 2D (SEM) and 3D (laser microscopy, LM) techniques. For the nanoscale level, ‘grains’ analysis is done using X-ray diffraction (XRD), revealing the defects, vacancies and swelled grains. Initially, emphasis is on the near-eutectic composition of salt mixtures of CeCl3 with NaCl as the carrier salt. Cerium trichloride (CeCl3) is an inactive surrogate of UCl3 and PuCl3. The results were measured for the specific salt mixture (70 mol% NaCl and 30 mol% CeCl3) in this work, establishing that microscopy and XRD are important techniques for measurement of the physical properties of salts component pellets. This work is of significance, as densities of fuel components affect the power evolution through reactivity and the average neutronic behaviour in zero power salt reactors.

AB - With growing interest in molten salts as possible nuclear fuel systems, knowledge of thermophysical properties of complex salt mixtures, e.g., NaCl-CeCl3, NaCl-UCl3 and NaCl-UCl4, informs understanding and performance modelling of the zero power salt reactor. Fuel density is a key parameter that is examined in a multiscale approach in this paper. In the zero power reactor ‘core’ (cm level), the relative fuel density is estimated for the fuel pin disposition, as well as a function of their pitch (strong effect). Fuel density of the ‘pellet’ (mm–µm level) is first estimated on a geometrical basis, then through tracking pores and cracks using 2D (SEM) and 3D (laser microscopy, LM) techniques. For the nanoscale level, ‘grains’ analysis is done using X-ray diffraction (XRD), revealing the defects, vacancies and swelled grains. Initially, emphasis is on the near-eutectic composition of salt mixtures of CeCl3 with NaCl as the carrier salt. Cerium trichloride (CeCl3) is an inactive surrogate of UCl3 and PuCl3. The results were measured for the specific salt mixture (70 mol% NaCl and 30 mol% CeCl3) in this work, establishing that microscopy and XRD are important techniques for measurement of the physical properties of salts component pellets. This work is of significance, as densities of fuel components affect the power evolution through reactivity and the average neutronic behaviour in zero power salt reactors.

U2 - 10.3390/jne5030026

DO - 10.3390/jne5030026

M3 - Journal article

VL - 5

SP - 420

EP - 435

JO - Journal of Nuclear Engineering

JF - Journal of Nuclear Engineering

SN - 2673-4362

IS - 3

ER -