Published 2013 | Version v1
Miscellaneous

Investigations into natural circulation driven heat removal systems

  • 1. Technische Univ. Dresden (Germany). Chair of Hydrogen and Nuclear Energy
  • 2. AREVA NP GmbH, Offenbach am Main (Germany)

Description

Passive safety systems can make an important contribution to decay heat removal in existing and next Generation NPP. Two-phase natural circulation systems have under certain circumstances instabilities which have to be analysed in detail. For this reason the test facility GENEVA has been constructed and commissioned at the TU Dresden. The experiments described in the experimental matrix will be started this year. First experimental data showed flow instabilities e.g. flashing as expected. Generic studies are necessary to examine two-phase flow and especially two-phase flow instabilities in further detail. The influence of subcooling and the diameters of downcomer and riser are of particular interest. These will help to evaluate the system behaviour of passive heat removal systems as well as their safety and reliability for nuclear reactors. (orig.)

Part of:
Annual meeting on nuclear technology 2013. Documentation

Additional details

Additional titles

Original title (English)
Jahrestagung Kerntechnik 2013. Dokumentation

Publishing Information

Imprint Title
Annual meeting on nuclear technology 2013. Documentation
Imprint Pagination
1142 p.
Journal Page Range
6 p.

Conference

Title
Annual meeting on nuclear technology 2013
Original Conference Title
Jahrestagung Kerntechnik 2013
Dates
14-16 May 2013
Place
Berlin (Germany)

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
45049769
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
AFTER-HEAT REMOVAL; COMPARATIVE EVALUATIONS; DESIGN; ENGINEERED SAFETY SYSTEMS; NATURAL CONVECTION; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; RELIABILITY; SAFETY ENGINEERING; STABILITY; SUBCOOLING; TEST FACILITIES; TRANSIENTS; TWO-PHASE FLOW
Descriptors DEC
CONVECTION; COOLING; ENERGY TRANSFER; ENGINEERING; EVALUATION; FLUID FLOW; HEAT TRANSFER; MASS TRANSFER; REMOVAL; SAFETY

Optional Information

Notes
Imprint:Jahrestagung Kerntechnik 2013. Dokumentation