Analytical benchmarks for verification of thermal-hydraulic codes based on sub-channel approach

Verification of a Viscous Computational Aeroacoustics Code using External Verification Analysis

“…which is recognized as the same expression that would have been found by differentiating each term in the right-hand side of ( 19) with respect to t. Knowing this, a general dependency relationship for the temporal and mixed spatial-temporal derivatives of the Navier-Stokes equations can quickly be determined by differentiating (19) with respect to t n and X a :…”

“…17,18 Instances of its use in non-CFD applications are less prevalent, but do exist. Merroun et al 19 showed how MMS could be used with a code simulating convective heat transfer in multiple channels (the code's application was nuclear reactor cooling), and Pautz 20 communicated results of applying MMS to a finite element code solving equations with applications to nuclear transport. Also, one of the FSI examples previously mentioned 16 had its origin in biomechanics problems.…”

“…Figure19. Magnitude of the amplification factor for each of the five time-marching schemes implemented in BASS.…”

Simulation of a TRIGA Reactor Core Blockage Using RELAP5 Code

“…The values of were taken from RELAP5 steady station calculation and Δ sat and sur were calculated using (1) and (2). The values for 100 kW and 265 kW are, respectively, These results means that the reactor regime is the subcooled nucleate boiling in which sur > sat , but fluid < sat .…”

“…The safety analysis of research reactors includes simulations of selected cases classified by the International Atomic Energy Agency, since the simulations are performed using nodalizations verified and validated by users of internationally recognized codes [1]. The thermal hydraulic analysis is considered as an essential aspect in the study of safety of nuclear power and research reactors, since it can predict proper working conditions, steady state and transient, thereby ensuring the safe operation of a nuclear reactor [2]. Among thermal hydraulic accidents are the loss of flow accident (LOFA) and loss of coolant accident (LOCA).…”