Results 31 to 40 of about 218 (131)
Conceptual Engineering of CARA Fuel Element with Negative Void Coefficient for Atucha II
Science and Technology of Nuclear Installations, Volume 2011, Issue 1, 2011., 2011 Experimentally validated void reactivity calculations were used to study the feasibility of a change in the design basis of Atucha II Nuclear Power Plant including the Large LOCA event. The use of CARA fuel element with burnable neutronic absorbers and enriched uranium is proposed instead of the original fuel. The void reactivity, refuelling costs, and
H. Lestani +3 more
wiley +1 more source
Role of RELAP/SCDAPSIM in Nuclear Safety
Science and Technology of Nuclear Installations, Volume 2010, Issue 1, 2010., 2010 The RELAP/SCDAPSIM code, designed to predict the behaviour of reactor systems during normal and accident conditions, is being developed as part of the international SCDAP Development and Training Program (SDTP). SDTP consists of nearly 60 organizations in 28 countries supporting the development of technology, software, and training materials for the ...
C. M. Allison +2 more
wiley +1 more source
Science and Technology of Nuclear Installations, Volume 2008, Issue 1, 2008., 2008 This paper provides a novel and robust methodology for determination of nuclear reactor trip setpoints which accounts for uncertainties in input parameters and models, as well as accounting for the variations in operating states that periodically occur.
D. R. Novog +2 more
wiley +1 more source
, 2014 Numerical computations of moderator flows inside calandria of the typical CANDU-6 reactor are presented here. The numerical model is based on incompressible Navier-Stokes equations in artificial compressibility formulation with dual time-stepping ...
SONAWANE, CR, MANDAL, JC
core +1 more source
Pressure Tubes: The Pressure Vessels in the CANDU Nuclear Power Reactor
, 1978 One of the main engineering characteristics of the CANDU nuclear-power reactor is the use of pressure tubes rather than one large pressure vessel to contain the fuel and coolant.
P.A. Ross-Ross
core +2 more sources
, 2015 Thermal contact conductance (TCC) is one of the most important parameters in determining the temperature distribution in contacting structures. Thermal contact conductance between the contacting structures depends on the mechanical properties of ...
PAWASKAR, DN +4 more
core +1 more source
High-temperature creep deformation evaluation in CANDU pressure tubes under a station black-out
, 2021 In this work the deformation of pressure tubes in CANDU6 nuclear reactor under a Station BlackOut event is analyzed. Firstly, the thermal–hydraulic simulation of the whole reactor is carried out using RELAP5Mod3 in order to get the spatial and temporal ...
Corzo, Santiago Francisco +2 more
core +1 more source
Evaluation of circulation and heat transfer in calandria tubes of crystallisation vacuum pans [PDF]
, 2005 This thesis investigates the importance of circulation and heat transfer in crystallisation vacuum pans that produce raw sugar in the sugar mill. The driving force for circulation and heat transfer occurs in the calandria tubes within vacuum pans ...
Rackemann, Darryn Wallace
core
, 2017 The core of a CANDU(1) (CANada Deuterium Uranium) pressurized heavy water reactor consists of a lattice of either 390 or 480 horizontal Zr-Nb pressure tubes, depending on the reactor design. These pressure tubes contain the fuel bundles.
Steven Xu, Cheng Liu, Douglas Scarth
core +1 more source
Modeling Film Boiling and Quenching on the Outer Surface of a Calandria Tube Following a Critical Break Loca in a CANDU Reactor [PDF]
, 2008 In a postulated critical break LOCA in a CANDU reactor it is possible that heatup of a pressure tube (PT) causes ballooning contact with the calandria tube (CT). Stored heat in the PT is transferred out, yielding a high PT-CT heat flux, which can cause
Jiang, Jian Tao
core