Pool boiling CHF enhancement by graphene-oxide nanofluid under nuclear coolant chemical environments
- 1. Interdisciplinary School of Green Energy, Ulsan National Institute of Science and Technology (UNIST), 100 Banyeon-ri, Eonyang-eup, Ulju-gun, Ulsan 689-798 (Korea, Republic of)
Description
Highlights: ► We investigate CHF limits of graphene-oxide nanofluids for IVR-ERVC. ► Graphene-oxide nanofluids were stable under ERVC coolant chemical environments. ► GO nanofluids enhanced CHF up to about 40–200% with heater orientation. - Abstract: External reactor vessel cooling (ERVC) for in-vessel retention (IVR) of corium as a key severe accident management strategy can be achieved by flooding the reactor cavity during a severe accident. In this accident mitigation strategy, the decay heat removal capability depends on whether the imposed heat flux exceeds critical heat flux (CHF). To provide sufficient cooling for high-power reactors such as APR1400, there have been some R and D efforts to use the reactor vessel with micro-porous coating and nanofluids boiling-induced coating. In present study, an experimental study has been conducted to investigate the viability of using graphene-oxide nanofluid under various coolant chemical environments to enhance CHF during ERVC. Pool boiling CHF experiments were carried out for the thin-wire heater with controlling the heater orientation from horizontal to vertical, or at 0 < θ < 90°. The dispersion stability of graphene-oxide nanofluid in the chemical conditions of flooding water that includes boric acid, lithium hydroxide (LiOH), and tri-sodium phosphate (TSP) was checked in terms of surface charge or zeta potential before the CHF experiments. Finally integral effects of graphene-oxide nanosheets and chemicals on CHF limits were investigated. Results showed that graphene-oxide nanofluids were very stable under ERVC coolant chemical environments and enhanced CHF limits up to about 40% at minimum at 90° of angle (vertical orientation) and about 200% at maximum at 0° of angle (horizontal orientation) in comparison to pure water.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2012.07.016Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2012.07.016;
- PII
- S0029-5493(12)00412-8;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 252
- Journal Page Range
- p. 184-191
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 44025334
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- ACCIDENT MANAGEMENT; AFTER-HEAT REMOVAL; BORIC ACID; COOLANTS; COOLING; CRITICAL HEAT FLUX; GRAPHITE; LITHIUM HYDROXIDES; MITIGATION; NANOSTRUCTURES; OXIDES; POOL BOILING; POROUS MATERIALS; POWER REACTORS; REACTOR VESSELS; SODIUM PHOSPHATES; WATER
- Descriptors DEC
- ALKALI METAL COMPOUNDS; BOILING; BORON COMPOUNDS; CARBON; CHALCOGENIDES; CONTAINERS; ELEMENTS; HEAT FLUX; HYDROGEN COMPOUNDS; HYDROXIDES; INORGANIC ACIDS; INORGANIC COMPOUNDS; LITHIUM COMPOUNDS; MANAGEMENT; MATERIALS; MINERALS; NONMETALS; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; PHOSPHATES; PHOSPHORUS COMPOUNDS; REACTORS; REMOVAL; SODIUM COMPOUNDS
Optional Information
- Copyright
- Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.