Published 2012 | Version v1
Miscellaneous

Analysis of steam generator tube leakage in an LFR design

  • 1. Royal Institute of Technology (KTH). Div. of Nuclear Power Safety, Stockholm (Sweden)

Description

No abstract prepared. Power Point presentation

Availability note (English)

Available at http://nordic-gen4.org/seminars/nordic-gen4-riso-2012-2/

Additional details

Publishing Information

Imprint Pagination
20 p.

Conference

Title
Nordic-Gen4 seminar
Dates
29-31 Oct 2012
Place
Risoe, Roskilde (Denmark)

INIS

Country of Publication
Denmark
Country of Input or Organization
Denmark
INIS RN
44000555
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Non-conventional Literature, Conference
Descriptors DEI
BUBBLES; FAST REACTORS; LEAD; LEAKS; POOL TYPE REACTORS; STEAM GENERATORS; TUBES; VOIDS
Descriptors DEC
BOILERS; ELEMENTS; EPITHERMAL REACTORS; METALS; REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS