Published 2005 | Version v1
Report

Superphenix - Creys Malville. Strategy for dismantling the reactor block

Creators

  • 1. EDF/CIDEN, Villeurbanne (France)

Description

This document describes the operations to be performed to dismantle the SPX reactor vessel. The first studies for dismantling the Superphenix power station reactor block have defined the broad outlines of the dismantling strategy an proposed a certain number of orientations. The period covers SPX reactor block dismantling, from the end of fuel unloading until complete dismantling of the installations. Two dismantling methods have been considered: -underwater dismanting (Reference scenario); - dismantling with the structures covered with sodium carbontae (Alternative scenario). In both cases, dismantling will be carried out 'from the top' through the reactor slab and will be preceded by a preliminary phase of sodium retention reduction followed by a phase of vessel internals carbonation. The dismantling studies are undertaken with a view to the work lasting eight years maximum. The work prior to reactor dismantling will last from the end of 2011, after sodium draining from the reactor, until the end of 2013. At present, the Superphenix dismantling work is planned to begin in 2014 and continue for a period of eight years. All the installations should have been dismantled by 2025. (author)

Part of:
Technical meeting on decommissioning of fast reactors after sodium draining. Working material

Additional details

Publishing Information

Imprint Title
Technical meeting on decommissioning of fast reactors after sodium draining. Working material
Imprint Pagination
750 p.
Journal Page Range
p. 516-548
Report number
TWG-FR--128

Conference

Title
Technical meeting on decommissioning of fast reactors after sodium draining
Dates
26-30 Sep 2005
Place
Cadarache (France)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
38003249
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FUEL MANAGEMENT; REACTOR DISMANTLING; REACTOR VESSELS; RETENTION; SODIUM; UNDERWATER; UNLOADING
Descriptors DEC
ALKALI METALS; CONTAINERS; DEMOLITION; ELEMENTS; LEVELS; MANAGEMENT; MATERIALS HANDLING; METALS; NUCLEAR MATERIALS MANAGEMENT

Optional Information

Notes
Includes PowerPoint presentation; 2 figs
Secondary number(s)
IAEA-TM--27329