|
Volumn 235, Issue 2-4, 2005, Pages 411-419
|
Consolidation of scientific and technological expertise to assess the reliability of reactor pressure vessel embrittlement prediction in particular for the arctic area plant (COBRA)
a a b b c c c c d d d e e e f f g
a
TECNATOM S A
(Spain)
|
Author keywords
[No Author keywords available]
|
Indexed keywords
ACCIDENT PREVENTION;
COOLING SYSTEMS;
EMBRITTLEMENT;
FINITE ELEMENT METHOD;
GAMMA RAYS;
HYDRAULICS;
IMPACT TESTING;
IRRADIATION;
NEUTRONS;
NUCLEAR FUELS;
NUCLEAR INSTRUMENTATION;
POSITION CONTROL;
PRESSURE VESSELS;
ARCTIC AREA PLANT;
IRRADIATED SURVEILLANCE;
NEUTRON FLUX;
REACTOR PRESSURE VESSELS (RPV);
NUCLEAR REACTOR ACCIDENTS;
|
EID: 19944429112
PISSN: 00295493
EISSN: None
Source Type: Journal
DOI: 10.1016/j.nucengdes.2004.08.062 Document Type: Conference Paper |
Times cited : (13)
|
References (4)
|