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Thermal hydraulic parametric investigation of decay heat removal from degraded core of a sodium cooled fast Breeder reactor
- Source :
- Nuclear Engineering and Design. 313:285-295
- Publication Year :
- 2017
- Publisher :
- Elsevier BV, 2017.
-
Abstract
- Ensuring post accident decay heat removal with high degree of reliability following a Core Disruptive Accident (CDA) is very important in the design of sodium cooled fast reactors (SFR). In the recent past, a lot of research has been done towards the design of an in-vessel core catcher below the grid plate to prevent the core debris reaching the main vessel in a pool type SFR. However, during an energetic CDA, the entire core debris is unlikely to reach the core catcher. A significant part of the debris is likely to settle in core periphery between radial shielding subassemblies and the inner vessel. Failure of inner vessel due to the decay heat can lead to core debris reaching the main vessel and threatening its integrity. On the other hand, retention of a part of debris in core periphery can reduce the load on main core catcher. Towards achieving an optimum design of SFR and safety evaluation, it is essential to quantify the amount of heat generating core debris that can be retained safely within the primary vessel. This has been performed by a mathematical simulation comprising solution of 2-D transient form of the governing equations of turbulent sodium flow and heat transfer with Boussinesq approximations. The conjugate conduction-convection model adopted for this purpose is validated against in-house experimental data. Transient evolutions of natural convection in the pools and structural temperatures in critical components have been predicted. It is found that 50% of the core debris can be safely accommodated in the gap between radial shielding subassemblies and inner vessel without exceeding structural temperature limit. It is also established that a single plate core catcher can safely accommodate decay heat arising due to ∼70% of the core debris by establishing natural circulation in the lower sodium pool. The influence of heat removal rate by natural circulation on availability of the number of decay heat exchangers (DHX) dipped in the upper pool is also analyzed. It is seen that the temperatures in the inner vessel, source plate and the maximum debris temperature do not increase significantly even when the DHXs are deployed 5 h after the accident, demonstrating the benefit of large thermal inertia of the pool.
- Subjects :
- Nuclear and High Energy Physics
Natural convection
business.industry
020209 energy
Mechanical Engineering
Nuclear engineering
02 engineering and technology
Structural engineering
Debris
Core (optical fiber)
Natural circulation
Nuclear Energy and Engineering
Heat transfer
0202 electrical engineering, electronic engineering, information engineering
Breeder reactor
Environmental science
General Materials Science
Decay heat
Safety, Risk, Reliability and Quality
business
Waste Management and Disposal
Core catcher
Subjects
Details
- ISSN :
- 00295493
- Volume :
- 313
- Database :
- OpenAIRE
- Journal :
- Nuclear Engineering and Design
- Accession number :
- edsair.doi...........46f046d2cc354c5e4c05ceb098b35187