skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Development of Cr cold spray–coated fuel cladding with enhanced accident tolerance

Journal Article · · Nuclear Engineering and Technology
ORCiD logo; ORCiD logo; ; ; ; ORCiD logo; ;

Accident-tolerant fuels (ATFs) are currently of high interest to researchers in the nuclear industry and in governmental and international organizations. One widely studied accident-tolerant fuel concept is multilayer cladding (also known as coated cladding). This concept is based on a traditional Zr-based alloy (Zircaloy-4, M5, E110, ZIRLO etc.) serving as a substrate. Different protective materials are applied to the substrate surface by various techniques, thus enhancing the accident tolerance of the fuel. This study focuses on the results of testing of Zircaloy-4 coated with pure chromium metal using the cold spray (CS) technique. In comparison with other deposition methods, e.g., Physical vapor deposition (PVD), laser coating, or Chemical vapor deposition techniques (CVD), the CS technique is more cost efficient due to lower energy consumption and high deposition rates, making it more suitable for industry-scale production. The Cr-coated samples were tested at different conditions (500°C steam, 1200°C steam, and Pressurized water reactor (PWR) pressurization test) and were precharacterized and postcharacterized by various techniques, such as scanning electron microscopy, Energy-dispersive X-ray spectroscopy (EDX), or nanoindentation; results are discussed. Results of the steady-state fuel performance simulations using the Bison code predicted the concept's feasibility. It is concluded that CS Cr coating has high potential benefits but requires further optimization and out-of-pile and in-pile testing.

Research Organization:
Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
NE0008416
OSTI ID:
1632988
Alternate ID(s):
OSTI ID: 1501542
Journal Information:
Nuclear Engineering and Technology, Journal Name: Nuclear Engineering and Technology Vol. 50 Journal Issue: 2; ISSN 1738-5733
Publisher:
ElsevierCopyright Statement
Country of Publication:
Korea, Republic of
Language:
English
Citation Metrics:
Cited by: 93 works
Citation information provided by
Web of Science

Cited By (2)

Effectiveness of Cr-Coated Zr-Alloy Clad in Delaying Fuel Degradation for a PWR During a Station Blackout Event journal August 2019
Oxidation behavior of RF magnetron sputtered Cr–SiC–Cr composites coating on zircaloy fuel cladding journal July 2019

Figures / Tables (17)

Fig. 1.(p. 2)figure Fig. 1.
Table 1(p. 2)table Table 1
Table 2(p. 2)table Table 2
Fig. 2.(p. 3)figure Fig. 2.
Fig. 3.(p. 3)figure Fig. 3.
Fig. 4.(p. 3)figure Fig. 4.
Table 3(p. 4)table Table 3
Fig. 5.(p. 5)figure Fig. 5.
Table 4(p. 5)table Table 4
Fig. 6.(p. 6)figure Fig. 6.
Fig. 7.(p. 6)figure Fig. 7.
Fig. 8.(p. 6)figure Fig. 8.
Fig. 10.(p. 7)figure Fig. 10.
Fig. 9.(p. 7)figure Fig. 9.
Table 5(p. 7)table Table 5
Table 6(p. 7)table Table 6
Fig. 11.(p. 8)figure Fig. 11.

Similar Records

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
Accident-Tolerant Fuel
Chromium
Cladding
Coating
Cold Spray
Nuclear Fuel