A pulse-controlled modified-burst test instrument for accident-tolerant fuel cladding

Cinbiz, M. Nedim; Brown, Nicholas R.; Terrani, Kurt A.; Lowden, Rick R.; Erdman, Donald

doi:10.1016/j.anucene.2017.05.058

Title: A pulse-controlled modified-burst test instrument for accident-tolerant fuel cladding

Journal Article · Sat Jun 03 00:00:00 EDT 2017 · Annals of Nuclear Energy (Oxford)

DOI:https://doi.org/10.1016/j.anucene.2017.05.058· OSTI ID:1362243

Cinbiz, M. Nedim ^[1]; Brown, Nicholas R. ^[2]; Terrani, Kurt A. ^[1]; Lowden, Rick R. ^[1]; Erdman, Donald ^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Pennsylvania State Univ., University Park, PA (United States)

Pellet-cladding mechanical interaction due to thermal expansion of nuclear fuel pellets during a reactivity-initiated accident (RIA) is a potential mechanism for failure of nuclear fuel cladding. To investigate the mechanical behavior of cladding during an RIA, we developed a mechanical pulse-controlled modified burst test instrument that simulates transient events with a pulse width from 10 to 300 ms. This paper includes validation tests of unirradiated and prehydrided ZIRLO cladding tubes. A ZIRLO cladding sample with a hydrogen content of 168 wt. ppm showed ductile behavior and failed at the maximum limits of the test setup with hoop strain to failure greater than 9.2%. ZIRLO samples showed high resistance to failure even at very high hydrogen contents (1,466 wt. ppm). When the hydrogen content was increased to 1,554 wt. ppm, brittle-like behavior was observed at a hoop strain of 2.5%. Preliminary scoping tests at room temperature with FeCrAl tubes were conducted to imitate the pulse behavior of transient test reactors during integral tests. The preliminary FeCrAl tests are informative from the perspective of characterizing the test rig and supporting the design of integral tests for current and potentially accident tolerant cladding materials.

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Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1362243

Alternate ID(s):: OSTI ID: 1416855

Journal Information:: Annals of Nuclear Energy (Oxford), Vol. 109; ISSN 0306-4549

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 11 works

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Cited By (2)

Atomic-scale interface structure of a Cr-coated Zircaloy-4 material Ribis, J.; Wu, A.; Brachet, J. -C. Journal of Materials Science, Vol. 53, Issue 14 https://doi.org/10.1007/s10853-018-2333-1	journal	April 2018
Transient Reactor Test Facility Advanced Transient Shapes Holschuh, Thomas; Woolstenhulme, Nicolas; Baker, Benjamin Nuclear Technology, Vol. 205, Issue 10 https://doi.org/10.1080/00295450.2018.1559712	journal	February 2019

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