Axial clad strain behavior of sphere-pac fuel pins /

ECCS calculations on fuel cladding.
Published: (1979)

Corrosion of research reactor aluminium clad spent fuel in water.
Published: (2003)

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

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)

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

Cladding rupture, swelling & coolant blockage as a result of a reactor accident.
Published: (1979)

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

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

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

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

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

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)

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

Experimental study of embrittlement of Zr-1%Nb VVER cladding under LOCA-relevant conditions /
by: Yegorova, L. A. (Larisa Alexandrovna)
Published: (2005)

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

Empirical modeling of uranium nitride fuels /
by: Brozak, Daniel Edward, 1963-
Published: (1987)

Irradiation effects in nuclear fuels /
by: Robertson, J. A. L., 1925-
Published: (1969)

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

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)

A new comparative analysis of LWR fuel designs /
by: O'Donnell, G. M., et al.
Published: (2001)

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

Material property correlations for the niobium-1% zirconium alloy /
by: Senor, David James, 1965-
Published: (1989)

Results of the post-irradiation examination of a highly-rated mixed oxide fuel rod from the MOL 7B experiment /
by: Coquerelle, M.
Published: (1980)

Zirconium in the nuclear industry : proceedings of the fourth International Conference /
Published: (1979)

Contact Detection and Constraints Enforcement for the Simulation of Pellet/Clad Thermo-Mechanical Contact in Nuclear Fuel Rods /
by: Lebrun-Grandie, Damien Thomas
Published: (2015)

Effects of radiation on nuclear materials and the nuclear fuel cycle : 24th volume /
Published: (2010)

FRAPCON-3.4 : a computer code for the calculation of steady state thermal-mechanical behavior of oxide fuel rods for high burnup /
by: Geelhood, K. J.
Published: (2011)