Title: Pool boiling critical heat flux studies of accident tolerant fuel cladding materials

Abstract

Pool boiling experiments have been performed at atmospheric pressure on potential accident tolerant fuel (ATF) cladding materials (Zirlo®, Cr coated Zirlo®, FeCrAl coated Zirlo®, and monolithic SiC) to evaluate the Critical Heat Flux (CHF) points. Corrosion resistant coatings of Cr and FeCrAl alloy were deposited on flat Zirlo® samples using cold spray technology. The as-prepared samples after uniform surface polishing were subjected to autoclave tests at 360 °C water and 18.6 MPa for 360 h to simulate prototypic corrosion of the ATF cladding materials in LWR normal operation. Surface characteristics potentially influencing CHF such as surface morphology, roughness, static contact angle, and surface chemistry were characterized using a suite of characterization methods including scanning electron microscopy, 3D optical profilometry, optical contact angle measurements, and x-ray photoelectron spectroscopy (XPS). Thermo-physical properties of the samples such as density, thermal conductivity, and heat capacity were measured by differential scanning calorimetry and laser flash thermal diffusivity measurement. FeCrAl coatings showed CHF values comparable to bare Zirlo® samples, while slightly lower CHF values were observed for Cr coated samples and bulk SiC flats (produced by chemical vapor deposition, CVD). As-deposited Cr coatings showed 67% higher CHF than the as-polished Cr coatings due to its highermore » surface roughness level. The autoclave testing for the prepared samples generally increased the CHF except for the surface polished Cr coatings. Similar CHF values of bare Zirlo®, FeCrAl coating, and CVD SiC samples were observed after autoclave test but there were negligible change CHF of Cr coatings. XPS studies indicated that the formation or deposition of a few monolayers of hydrophobic carbonaceous species on surface can affect CHF values. The trends in CHF data are discussed in terms of evolution of the surface characteristics of the ATF materials.« less

Authors:

Yeom, Hwasung ^[1]; Gutierrez, Emilio ^[1]; Jo, HangJin ^[2]; Zhou, Yimin ^[1]; Mondry, Kaya ^[1]; Sridharan, Kumar ^[3]; Corradini, Michael ^[1]

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+ Show Author Affiliations

1. Univ. of Wisconsin, Madison, WI (United States). Dept. of Engineering Physics
2. Pohang Univ. of Science and Technology (POSTECH) (Korea, Republic of). Dept. of Mechanical Engineering. Division of Advanced Nuclear Engineering
3. Univ. of Wisconsin, Madison, WI (United States). Dept. of Engineering Physics; Univ. of Wisconsin, Madison, WI (United States). Dept. of Materail Science and Engineering

Publication Date:

Mon Nov 02 00:00:00 EST 2020

Research Org.:

Univ. of Wisconsin, Madison, WI (United States)

Sponsoring Org.:

USDOE Office of Nuclear Energy (NE)

OSTI Identifier:

1850529

Alternate Identifier(s):

OSTI ID: 1776142

Grant/Contract Number:  

NE0008681

Resource Type:

Accepted Manuscript

Journal Name:

Nuclear Engineering and Design

Additional Journal Information:

Journal Volume: 370; Journal Issue: C; Journal ID: ISSN 0029-5493

Publisher:

Elsevier

Country of Publication:

United States

Language:

English

Subject:

73 NUCLEAR PHYSICS AND RADIATION PHYSICS; Nuclear Science & Technology; Critical heat flux (CHF); Surface characteristics; Accident tolerant fuel (ATF) cladding; Cold spray coating; Autoclave test