Quenching behaviour of hot zircaloy tube
- 1. Reactor Engineering Division, Bhabha Atomic Research Centre, Mumbai (India)
Description
The quenching process plays a very important role in case of safety of nuclear reactors. During large break Loss of Coolant Accident in a nuclear reactor, the cooling water from the system is lost. Under this condition, cold water is injected from emergency core cooling system. Quenching behaviour of such heated rod bundle is really complex. It is well known that nanofluids have better heat removal capability and high heat transfer coefficient owing to enhanced thermal properties. Alumina nano-particles result in better cooling abilities compared with the traditionally used quenching media. In this paper, the authors have carried out experiments on quenching behaviour of hot zircaloy tube with demineralized water and nanofluids. It was observed that, the tube got quenched within few seconds even with the presence of decay heat and shows slightly reduced quenching time compared with DM water. (author)
Additional details
Publishing Information
- Publisher
- Indian Space Research Organisation
- Imprint Place
- Trivandrum (India)
- Imprint Title
- Proceedings of the twenty third national heat and mass transfer conference and first international ISHMT-ASTFE heat and mass transfer conference: souvenir and book of abstracts
- Imprint Pagination
- 269 p.
- Journal Page Range
- p. 185
Conference
- Title
- 23. national heat and mass transfer conference; ISHMT-ASTFE: international heat and mass transfer conference
- Acronym
- IHMTC-2015
- Dates
- 17-20 Dec 2015
- Place
- Trivandrum (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 48043267
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT; ECCS; FUEL RODS; HEAT TRANSFER; LOSS OF COOLANT; QUENCHING; REACTOR COOLING SYSTEMS; ZIRCALOY
- Descriptors DEC
- ACCIDENTS; ALLOYS; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; FUEL ELEMENTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; TRANSITION ELEMENT ALLOYS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS