PATH - An experimental facility for natural circulation heat transfer studies related to Post Accident Thermal Hydraulics
Creators
- 1. Safety Engineering Division, Nuclear and Safety Engineering Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)
- 2. Experimental Analysis Section, Nuclear and Safety Engineering Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)
- 3. Nuclear and Safety Engineering Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)
- 4. Indira Gandhi Centre for Atomic Research, Kalpakkam (India)
Description
Highlights: → We have commissioned and tested 1:4 FBR water model for natural convection studies. → Study is focused on PAHR after severe accident. → Accurate online temperature measurements are made to study transient behavior. → Commissioning results for a case of 12 kW are highlighted. - Abstract: In fast reactor safety post accident heat removal assessment assumes importance to ensure integrity of the structural components. It is essential to demonstrate the passive built-in heat removal capabilities of the reactor in the event of a core disruptive accident. This paper details the commissioning aspect of Post Accident Thermal Hydraulics (PATH) experimental facility that is a scaled 1:4 water model of Prototype Fast Breeder Reactor (PFBR) India, to investigate heat removal by the natural convection with water as working fluid. This paper presents experimental temperature mapping and numerical methodology to evolve transient response of the system. Preliminary commissioning results for a case of 12 kW heat source is highlighted.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2011.06.054Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2011.06.054;
- PII
- S0029-5493(11)00539-5;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 241
- Journal Issue
- 9
- Journal Page Range
- p. 3839-3850
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- 7. European Commission conference on Euratom research and training in reactor systems
- Acronym
- Fission Safety 2009
- Dates
- 22-24 Jun 2009
- Place
- Prague (Czech Republic)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43050162
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; FBR TYPE REACTORS; HEAT SOURCES; INDIA; NATURAL CONVECTION; REACTOR CORE DISRUPTION; TEMPERATURE MEASUREMENT; TEST FACILITIES; THERMAL HYDRAULICS; WORKING FLUIDS
- Descriptors DEC
- ACCIDENTS; ASIA; BREEDER REACTORS; CONVECTION; DEVELOPING COUNTRIES; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FLUID MECHANICS; FLUIDS; HEAT TRANSFER; HYDRAULICS; MASS TRANSFER; MECHANICS; REACTOR ACCIDENTS; REACTORS; REMOVAL
Optional Information
- Copyright
- Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.