Results 61 to 70 of about 8,892 (145)
Iani Gruteri varii discursus; Sive Prolixiores Commentarii ad aliquot insigniora loca Taciti. atque Onosandri ; [1] [PDF]
IANI GRUTERI VARII DISCURSUS; SIVE PROLIXIORES COMMENTARII AD ALIQUOT INSIGNIORA LOCA TACITI. ATQUE ONOSANDRI ; [1] Iani Gruteri varii discursus (-) Iani Gruteri varii discursus; Sive Prolixiores Commentarii ad aliquot insigniora loca Taciti ...
Gruterus, Janus
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Iani Gruteri varii discursus; Sive Prolixiores Commentarii ad aliquot insigniora loca Taciti ; 2 [PDF]
IANI GRUTERI VARII DISCURSUS; SIVE PROLIXIORES COMMENTARII AD ALIQUOT INSIGNIORA LOCA TACITI ; 2 Iani Gruteri varii discursus (-) Iani Gruteri varii discursus; Sive Prolixiores Commentarii ad aliquot insigniora loca Taciti ; 2 (2) (1 ...
Gruterus, Janus
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Hydrogen motion in Zircaloy-4 cladding during a LOCA transient
, 2016 International audienceHydrogen and oxygen are key elements influencing the embrittlement of zirconium-based nuclear fuel cladding during the quench phase following a Loss Of Coolant Accident (LOCA).
Antoine, A. +7 more
core +1 more source
Uncertainty analysis for the K-reactor FI-LOCA limits [PDF]
, 1992 A postulated accident scenario for the Savannah River Site (SRS) K-reactor is a Double Ended Guillotine Break Loss of Coolant Accident (DEGB/LOCA) due to a coolant pipe break at the plenum inlet.
Hardy, B. J.
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Safety Investigation of in-box LOCA for DEMO Reactor: Experiments and Analyses
, 2017 The aim of this Ph.D. thesis work is the safety investigation of in-box Loss Of Coolant Accident for the Water Cooled Lithium Lead breeding blanket concept in DEMO reactor. The research work, conducted at ENEA C.R.
EBOLI, MARICA
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PWR representative behavior during a LOCA [PDF]
, 1981 To date, there has been substantial analytical and experimental effort to define the margins between design basis loss-of-coolant accident (LOCA) behavior and regulatory limits on maximum fuel rod cladding temperature and deformation.
Allison, C.M.
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, 2010 [[abstract]]According to Maanshan Unit 1 plant probabilistic risk assessment (PRA), the small loss-of-coolant accident (LOCA) S2WH is ranked third in frequency among postulated accidents Maanshan-1 is a 2775-MW(thermal), three-loop Westinghouse ...
C.C. Chen;T.K. Wang;S.C. Chiang
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Estimation of LOCA Break Size Using Cascaded Fuzzy Neural Networks
, 2016 Operators of nuclear power plants may not be equipped with sufficient information during a loss-of-coolant accident (LOCA), which can be fatal, or they may not have sufficient time to analyze the information they do have, even if this information is ...
Kwae Hwan Yoo +7 more
core +1 more source
, 2012 loca Caldwell, 1937 Type locality: USA, Arizona, California, Colorado, Illinois, Iowa, New Mexico, Oregon, Tennessee, Washington, Washington DC. Additional distribution: Canada, Alberta, Manitoba Host plant: Polygonum erectum.Published as part of ...
Hoddle, Mark S. +2 more
core +1 more source
Fuel rod stored energy estimates for the LOFT LOCA tests [PDF]
, 1980 Loss-of-coolant accident (LOCA) tests performed in the Loss-of-Fluid Test (LOFT) Facility provide an important data base for verification of thermal-hydraulic computer models.
Driskell, W. E. +2 more
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