Published May 2010
| Version v1
Book
Analysis of the counter-flow restriction for the emergency coolant injection in case of one-phase natural circulation using ANSYS CFX
Creators
- 1. TUEV NORD SysTec GmbH und Co. KG, Hamburg (Germany). Gruppe Thermofluiddynamik
Description
In case of a small leak of the primary circuit in a PWR plant coolant medium flows into the containment causing pressure increase and triggering reactor scram and eventually emergency coolant injection. The transport of the after-heat is assured by a one-phase or two-phase natural circulation in the coolant loops. The authors describe the CFD (computed fluid dynamics) modeling of the UPTF-TRAM A3 test concerning the counter-flow restriction for the emergency coolant injection in case of one-phase natural circulation results using the CFD code ANSYS CFX. The results of the CFD analysis agrees in large parts with the experimental results.
Additional details
Additional titles
- Original title (German)
- Analyse der Gegenstrombegrenzung einer Notkuehleinspeisung bei einphasigem Naturumlauf mit ANSYS CFX
Publishing Information
- Publisher
- Inforum Verlag
- Imprint Place
- Bonn (Germany)
- Imprint Title
- Annual meeting on nuclear technology 2010. Documentation
- Imprint Pagination
- 1017 p.
- Journal Page Range
- 7 p.
Conference
- Title
- Annual meeting on nuclear technology 2010
- Original Conference Title
- Jahrestagung Kerntechnik 2010
- Dates
- 4-6 May 2010
- Place
- Berlin (Germany)
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 43018447
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; ACCIDENT MANAGEMENT; BOUNDARY CONDITIONS; COMPUTERIZED SIMULATION; COOLANT LOOPS; COUNTERFLOW SYSTEMS; ECCS; FINITE ELEMENT METHOD; FLUID MECHANICS; LOSS OF COOLANT; NATURAL CONVECTION; SAFETY INJECTION; TEST FACILITIES; THERMAL HYDRAULICS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; COMPUTER CODES; CONVECTION; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; MANAGEMENT; MASS TRANSFER; MATHEMATICAL SOLUTIONS; MECHANICS; NUMERICAL SOLUTION; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; SIMULATION
Optional Information
- Notes
- Imprint:Jahrestagung Kerntechnik 2010. Dokumentation