Methodologies to assess potential lifetime limits for extended burnup nuclear fuel /

Uncertainties in predicted isotopic compositions for high burnup PWR spent nuclear fuel /
Published: (2011)

Review of information for spent nuclear fuel burnup confirmation /
Published: (2009)

Criticality analysis of assembly misload in a PWR burnup credit cask /
by: Wagner, J. C.
Published: (2008)

Mechanical fatigue testing of high-burnup fuel for transportation applications /
by: Wang, Jy-An, et al.
Published: (2017)

Experimental study of narrow pulse effects on the behavior of high burnup fuel rods with Zr-1%Nb cladding and UO₂ fuel (VVER type) under reactivity-initiated accident conditions /
by: Yegorova, L. A. (Larisa Alexandrovna)
Published: (2006)

Dry storage and transportation of high-burnup spent nuclear fuel : draft report for comment /
by: Ahn, T. M.
Published: (2018)

Impact of high burnup uranium oxide and mixed uranium-plutonium oxide water reactor fuel on spent fuel management /
by: Lovasic, Z.
Published: (2011)

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

Limited burnup credit in criticality safety analysis : a comparison of ISG-8 and current international practice /
by: Gauld, I. C.
Published: (2001)

Impact of operating parameters on extended BWR burnup credit /
by: Ade, Brian J.
Published: (2018)

STARBUCS : a prototypic SCALE control module for automated criticality safety analyses using burnup credit /
Published: (2001)

Axial moderator density distributions, control blade usage, and axial burnup distributions for extended BWR burnup credit /
by: Marshall, William (B. J.)
Published: (2016)

Implications from the phenomenon identification and ranking tables (PIRTs) and suggested research activities for high burnup fuel /
by: Meyer, R. O. (Ralph O.)
Published: (2001)

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)

US commercial spent nuclear fuel assembly characteristics : 1968-2013 /
by: Hu, Jianwei
Published: (2016)

Study of the effect of integral burnable absorbers for PWR burnup credit /
Published: (2001)

Burn-up determination of nuclear fuel by high-resolution gamma-spectroscopy /
Published: (1964)

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

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)

Storage of spent nuclear fuel.
Published: (2012)

SP1TFRE-SP-100 transient fuel rod evaluation code /
by: Carpenter, David Charles, 1955-
Published: (1986)

An approach for validating actinide and fission product burnup credit criticality safety analyses--isotopic composition predictions /
by: Radulescu, G.
Published: (2012)

Evaluation of fuel rod characterization for transient fuel modeling /
by: Bechler, Eric Wayne, 1964-
Published: (1989)

Fission gas behaviour in water reactor fuels.
Published: (2002)

FRAPCON-3.4 : integral assessment /
by: Geelhood, K. J.
Published: (2011)

Spent nuclear fuel transportation.
Published: (2000)

Optimization of water chemistry to ensure reliable water reactor fuel performance at high burnup and in ageing plant (FUWAC).
Published: (2011)

ATWS-enclosing letter to GE, with NUREG-0460, vol. 3.
Published: (1979)

ATWS.
Published: (1979)

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)

Advances in applications of burnup credit to enhance spent fuel transportation, storage, reprocessing and disposition : proceedings of a technical meeting held in London, 29 August- 2 September 2005.
Published: (2007)

Safety of spent fuel storage.
Published: (2017)

An approach for validating actinide and fission product burnup credit criticality safety analyses--criticality (k[subscript eff]) predictions /
Published: (2012)

Vergleich der Abbrandbestimmungen mittels Sondenaktivierung und Gamma-Spektroskopie für ein MTR-Element /
by: Buba, L.
Published: (1965)

Fuel rod performance uncertainty analysis during overpressurization transient for Kuosheng Nuclear Power Plant with TRACE/FRAPTRAN/Dakota codes in SNAP interface /
by: Shih, Chunkuan
Published: (2016)

Inadvertent removal of fuel assemblies from the reactor core.
Published: (1990)