Thermal hydraulic consequences of primary pipe rupture
- 1. Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam (India)
Description
Thermal hydraulic analyses of primary pump pipe rupture event have been carried out with the objective of (i) estimating the temperature rise in the fuel, cladding and coolant, (ii) investigation of possible flow redistribution in subassemblies and (iii) investigation of the formation of vapour bubbles due to flashing, resulting in reactivity addition in the core. For this purpose one dimensional studies using thermal and hydraulic models of the core SA and primary sodium circuit, three dimensional studies of grid plate using the CFD code PHOENICS and one dimensional studies using pressure transient codes have been carried out. Analysis indicates that the core flow is reduced to 30% during the transient and specified temperature limits of this category of events are respected. There is no flow redistribution among various subassemblies and no formation of vapour in subassemblies. (author)
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Additional details
Identifiers
Publishing Information
- ISBN
- 92-0-109104-4
- Imprint Title
- Primary coolant pipe rupture event in liquid metal cooled reactors. Proceedings of a technical meeting
- Imprint Pagination
- 17 p.
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1406
Conference
- Title
- Technical meeting on primary coolant pipe rupture event in liquid metal cooled reactors
- Dates
- 13-17 Jan 2003
- Place
- Kalpakkam (India)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36030768
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S43: PARTICLE ACCELERATORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FINITE DIFFERENCE METHOD; HEAT FLUX; LOSS OF FLOW; P CODES; PIPES; PRIMARY COOLANT CIRCUITS; SODIUM; TEMPERATURE GRADIENTS; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ACCIDENTS; ALKALI METALS; CALCULATION METHODS; COMPUTER CODES; COOLING SYSTEMS; ELEMENTS; ENERGY SYSTEMS; FLUID MECHANICS; HYDRAULICS; ITERATIVE METHODS; MATHEMATICAL SOLUTIONS; MECHANICS; METALS; NUMERICAL SOLUTION; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; TUBES
Optional Information
- Notes
- 7 refs, 13 figs, 1 tab