There is a newer version of the record available.

Published 2005 | Version v1
Report Metadata-only

Development and verification of safety analysis code for ADS

Creators

  • 1. Kyushu University, Fukuoka (Japan)
  • 2. Forschungszentrum Karlsruhe, Karlsruhe (Germany)

Description

The goal of the study is the extension of a safety analysis code for sodium LMFR to ADS (thermal-hydraulics models). Experimental studies for key thermal-hydraulic phenomena (CRP work) are directed to model development and verification for molten-metal freezing phenomena. The modelling of material properties covers coolant of lead-bismuth eutectic (LBE) alloy and advanced fuels such as CERCER and CERMET

Part of:
Technical Meeting (Research Coordination Meeting) of the Coordinated Research Project (CRP) on 'Studies of advanced reactor technology options for effective incineration of radioactive waste'. Working material

Additional details

Publishing Information

Imprint Title
Technical Meeting (Research Coordination Meeting) of the Coordinated Research Project (CRP) on 'Studies of advanced reactor technology options for effective incineration of radioactive waste'. Working material
Imprint Pagination
524 p.
Journal Page Range
p. 320-333
Report number
TWG-FR--124

Conference

Title
Technical meeting (Research Coordination Meeting) of the Coordinated Research Project (CRP) on 'Studies of advanced reactor technology options for effective incineration of radioactive waste'
Dates
22-26 Nov 2004
Place
Hefei (China)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
37062910
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ALLOYS; BISMUTH; COOLANTS; EUTECTICS; FREEZING; LEAD; LMFBR TYPE REACTORS; NUCLEAR FUELS; SAFETY ANALYSIS; SODIUM; THERMAL HYDRAULICS; VERIFICATION
Descriptors DEC
ALKALI METALS; BREEDER REACTORS; ELEMENTS; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID MECHANICS; FUELS; HYDRAULICS; LIQUID METAL COOLED REACTORS; MATERIALS; MECHANICS; METALS; PHASE TRANSFORMATIONS; REACTOR MATERIALS; REACTORS

Optional Information

Notes
Published as Power Point presentation only
Secondary number(s)
IAEA-RC--870.2