Published 2019
| Version v1
Book
Calculation of rewetting velocity and heat transfer coefficients for nuclear thoria fuel with applicability in fuel design and engineering
Creators
- 1. Simran Villa, Sector 27, Kharghar, Navi Mumbai (India)
- 2. Reactor Engineering Division, Bhabha Atomic Research Centre, Mumbai (India)
Description
When loss of coolant accident (LOCA) in a Thoria fuelled nuclear reactor occurs and injection of coolant from ECCS follows the value of wet region heat transfer coefficient (HTC) plays important role in ensuring the integrity of clad. Objective of this work is the prediction of wet region HTC. Detailed description of model, assumptions, description of numerical solution of the equation, results, discussions and more references will be made available in this paper
Additional details
Publishing Information
- Publisher
- Bhabha Atomic Research Centre
- Imprint Place
- Mumbai (India)
- Imprint Title
- Proceedings of the conference on indigenous nuclear fuel program in India - achievements, status and prospects: extended abstracts cum souvenir
- Imprint Pagination
- 408 p.
- Journal Page Range
- p. 213-214
Conference
- Title
- conference on indigenous nuclear fuel program in India - achievements, status and prospects
- Acronym
- INFPIN-2019
- Dates
- 31 Jan - 2 Feb 2019
- Place
- Mumbai (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 50070724
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLADDING; ECCS; HEAT TRANSFER; LOSS OF COOLANT; NUCLEAR FUELS; REWETTING; THORIUM; VELOCITY
- Descriptors DEC
- ACCIDENTS; ACTINIDES; DEPOSITION; ELEMENTS; ENERGY SOURCES; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; FUELS; MATERIALS; METALS; REACTOR ACCIDENTS; REACTOR MATERIALS; REACTOR PROTECTION SYSTEMS; SURFACE COATING