Fluid Flow Characteristic Simulation of the Original TRIGA 2000 Reactor Design Using Computational Fluid Dynamics Code
- National Nuclear Energy Agency of Indonesia, Jl. Tamansari 71, Bandung, 40132 (Indonesia)
Common energy crisis has modified the national energy policy which is in the beginning based on natural resources becoming based on technology, therefore the capability to understanding the basic and applied science is needed to supporting those policies. National energy policy which aims at new energy exploitation, such as nuclear energy is including many efforts to increase the safety reactor core condition and optimize the related aspects and the ability to build new research reactor with properly design. The previous analysis of the modification TRIGA 2000 Reactor design indicates that forced convection of the primary coolant system put on an effect to the flow characteristic in the reactor core, but relatively insignificant effect to the flow velocity in the reactor core. In this analysis, the lid of reactor core is closed. However the forced convection effect is still presented. This analysis shows the fluid flow velocity vector in the model area without exception. Result of this analysis indicates that in the original design of TRIGA 2000 reactor, there is still forced convection effects occur but less than in the modified TRIGA 2000 design.
- OSTI ID:
- 21410486
- Journal Information:
- AIP Conference Proceedings, Vol. 1244, Issue 1; Conference: ICANSE 2009: 2. international conference on advances in nuclear science and engineering 2009, Bandung (Indonesia), 3-4 Nov 2009; Other Information: DOI:; (c) 2010 American Institute of Physics; ISSN 0094-243X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
COMPUTERIZED SIMULATION
COOLANTS
ENERGY CONSERVATION
ENERGY POLICY
FISSION
FLUID FLOW
FLUID MECHANICS
FORCED CONVECTION
MODIFICATIONS
NUCLEAR ENERGY
PRIMARY COOLANT CIRCUITS
REACTOR CORES
REACTOR SAFETY
RESEARCH REACTORS
RESOURCES
TRIGA TYPE REACTORS
VELOCITY
CONVECTION
COOLING SYSTEMS
ENERGY
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
GOVERNMENT POLICIES
HEAT TRANSFER
HOMOGENEOUS REACTORS
HYDRIDE MODERATED REACTORS
MASS TRANSFER
MECHANICS
NUCLEAR REACTIONS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SIMULATION
SOLID HOMOGENEOUS REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS