Cladding rupture, swelling & coolant blockage as a result of a reactor accident.

Corrosion of research reactor aluminium clad spent fuel in water.
Published: (2009)

Axial clad strain behavior of sphere-pac fuel pins /
by: Thomas, James Kelly, 1962-
Published: (1986)

Cracking of cladding and its heat-affected zone in the base metal of a reactor vessel head.
Published: (1990)

ECCS calculations on fuel cladding.
Published: (1979)

Loss of particles through a clad breach in a simulated sphere-pac fuel pin /
by: Sunderland, Dion Julian, 1957-
Published: (1985)

Assessment of current test methods for post-LOCA cladding behavior /
by: Billone, Michael C.
Published: (2012)

Delayed hydride cracking of zirconium alloy fuel cladding.
Published: (2010)

Report on ECCS cladding models, NUREG-0630.
Published: (1980)

Cracking in charging pump casing cladding.
Published: (1980)

Data base on the behavior of high burnup fuel rods with Zr-1%Nb cladding and UO₂ fuel (VVER type) under reactivity accident conditions.
by: Yegorova, L. A. (Larisa Alexandrovna)
Published: (1999)

Cladding behavior during postulated loss-of-coolant accidents /
by: Billone, M. C.
Published: (2016)

Material property correlations : comparisons between FRAPCON-3.5, FRAPTRAN-1.5, and MATRO /
by: Luscher, W. G. (Walter G.), 1979-, et al.
Published: (2014)

Metallurgical and mechanical properties of thorium-doped Ir-0.3% W alloys /
by: Liu, C. T. (Chain Tsuan), 1937-
Published: (1980)

FRAPCON-3.5 /
by: Geelhood, K. J., et al.
Published: (2014)

Adaptation of USNRC's FRAPTRAN and IRSN's SCANAIR transient codes and updating of MATPRO package for modeling of LOCA and RIA validation cases with Zr-1%Nb (VVER type) cladding /
by: Shestopalov, A., et al.
Published: (2003)

Mechanical properties of unirradiated and irradiated Zr-1% Nb cladding : procedures and results of low temperature biaxial burst tests and axial tensile tests /
by: Kaplar, E. P. (Evgeniĭ Petrovich)
Published: (2001)

Control of stainless steel weld cladding of low-alloy steel components.
Published: (2011)

Ultrasonic phased array assessment of the interference fit and leak path of the North Anna Unit 2 control rod drive mechanism nozzle 63 with destructive validation /
by: Crawford, S. L.
Published: (2012)

An evaluation of thermal modeling techniques utilized for nuclear fuel rods /
by: Simmons, Jeffrey Warren, 1963-
Published: (1989)

FRAPTRAN-1.5 /
by: Geelhood, K. J., et al.
Published: (2014)

Zirconium in the nuclear industry : sixth International Symposium sponsored by ASTM Committee B-10 on Reactive and Refractory Metals, Vancouver, B.C., 28 June-1 July 1982 /
Published: (1984)

Zirconium in the nuclear industry : eighth international symposium /
Published: (1989)

Zirconium in the nuclear industry : 15th international symposium /
Published: (2009)

Zirconium in the nuclear industry : thirteenth international symposium /
Published: (2002)

Zirconium in the nuclear industry : 16th international symposium /
Published: (2011)

Zirconium in the nuclear industry : tenth International Symposium /
Published: (1994)

Zirconium in the nuclear industry : fourteenth international symposium /
Published: (2006)

Zirconium in the nuclear industry : 20th international symposium /
Published: (2023)

Zirconium in the nuclear industry : eleventh international symposium /
Published: (1996)

Zirconium in the nuclear industry : 17th international symposium /
Published: (2015)

Modification of USNRC's FRAP-T6 fuel rod transient code for high burnup VVER fuel /
by: Shestopalov, A.
Published: (1999)

Durability of cladding : a state of the art report /
by: Ryan, P. A.
Published: (1994)

Durability of cladding : a state of art report /
by: Ryan, P. A.
Published: (1994)

Rod bundle heat transfer facility two-phase mixture level swell and uncovery test experiments data report /
by: Hochreiter, L. E.
Published: (2016)

Reactor accidents : nuclear safety and the role of institutional failure /
by: Mosey, David
Published: (1990)

Examination of spent PWR fuel rods after 15 years in dry storage /
Published: (2003)