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Prospects of chemical vapor grown silicon carbide thin films using halogen-free single sources in nuclear reactor applications: A review

Published online by Cambridge University Press:  31 July 2012

Jayaprakasam Selvakumar*
Affiliation:
Powder Metallurgy Division, Bhabha Atomic Research Centre, Navi Mumbai 400 705, India
Dakshinamoorthy Sathiyamoorthy
Affiliation:
Powder Metallurgy Division, Bhabha Atomic Research Centre, Navi Mumbai 400 705, India
*
a)Address all correspondence to this author. e-mail: jselva@barc.gov.in

Abstract

Next-generation fission and fusion nuclear reactor materials will be exposed to very high temperatures, intense neutron radiation, corrosive environments, and, mostly, all three at once. Grand opening will be given to the material, if they have stability at high temperature operating favorable in the extreme environments, self-healing, thermal as well as irradiation properties. Owing to the superior properties of silicon carbide, nuclear scientists are closely evaluating SiC-based materials for various applications in nuclear reactors. In the present perspective, relevant properties, challenging issues, and recommendations are emphasized. Based on our recent experiments, attempt to solve various uses on SiC-based materials in nuclear applications is described in detail.

Information

Type
Review
Copyright
Copyright © Materials Research Society 2012
Figure 0

SCHEME 1. Lateral view of TRISO layers deposited on kernel.

Figure 1

SCHEME 2. Pictorial view: Steam reaction on Zircaloy tube (cladding or fuel tube).

Figure 2

FIG. 1. Research and development on SiC over years.

Figure 3

SCHEME 3. Stability diagram of polytype as a function of temperature.

Figure 4

TABLE I. A review on CVD of SiC from halogen-free (alkylsilane) sources.

Figure 5

FIG. 2. Semiempirically (using PM3 Hamiltonian) optimized molecular structures of alkylsilane: used as a SiC sources in various CVD experiments (Table I).

Figure 6

FIG. 3. SiC protective layer development using a halogen-free CVD source (a) modified CVD experimental setup and processes; (b) SiC on zirconia particles (surrogate material): uncoated and coated (at 1373 K) zirconia particles and surface morphology; (c) SiC coating on Zircaloy tube (cladding): uncoated and coated (at 1023 K) Zircaloy tubes and surface morphology.

Figure 7

SCHEME 4. Potentially identified CVD source sublimator/evaporators: (a) conventional solid sublimator; (b) liquid evaporator; and (c) efficient FB sublimator.