Published April 2019 | Version v1
Report

Summary on SCWR Materials Research Activities Performed in EC-JRC

Creators

Description

This work is a summary of experimental activities on SCWR materials research performed in EC-JRC in 2014-2016. The common objective is selection of fuel cladding and internals materials including characterization of general corrosion resistance of pre-selected austenitic stainless, characterization of sensors, characterization of SCC resistance of preselected materials and development of tools for future qualification testing. The achieved results are presented and discussed. At the end future plans are introduced

Part of:
Status of Research and Technology Development for Supercritical Water Cooled Reactors. Companion CD-ROM

Additional details

Publishing Information

ISBN
978-92-0-101919-6
Imprint Title
Status of Research and Technology Development for Supercritical Water Cooled Reactors. Companion CD-ROM
Imprint Pagination
[1 CD-ROM]
Journal Page Range
1 p.
ISSN
1011-4289
Report number
IAEA-TECDOC--1869(COMPANION CD-ROM)

Conference

Title
2. Technical Meeting on Heat Transfer, Thermal Hydraulics and System Design for SCWRs; 3. Technical Meeting on Materials and Chemistry for SCWRs
Dates
22-24 Aug 2016; 10-14 Oct 2016
Place
Sheffield (United Kingdom); Rez (Czech Republic)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
51003800
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AUSTENITIC STEELS; CLADDING; CORROSION RESISTANCE; NUCLEAR FUELS; SENSORS; TESTING
Descriptors DEC
ALLOYS; CARBON ADDITIONS; DEPOSITION; ENERGY SOURCES; FUELS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; REACTOR MATERIALS; STEELS; SURFACE COATING; TRANSITION ELEMENT ALLOYS

Optional Information

Notes
Abstract only; Presentation also included