Published 2003 | Version v1
Report

Implementation of stage-3 decommissioning of the Triton Facility

  • 1. CEA Fontenay-aux-Roses, USLT/STL, Fontenay-aux Roses Cedex (France)

Description

Full text: An extensive decommissioning program has been launched by the French Atomic Energy Commission (CEA), including decommissioning of nuclear facilities related to the front-end and the back-end of the nuclear fuel cycle, and experimental reactors. This program includes the stage-3 decommissioning of the Triton facility, comprising two piles, Triton and Nereide, and a hot cell, located at the Fontenay-aux-Roses research centre. This facility was built in the late 1950s, primarily for R and D activities related to neutron physics studies, and radiological shielding experiments. As of 1982, stage-2 decommissioning started, was achieved in 1986 and since that date, no work has been done in the facility. This paper describes the extensive studies carried out to acquire a better knowledge of the facility radiological status, in order to set up dismantling scenarios and to reduce generated radioactive waste quantities. An overview of the selected dismantling scenario is provided, followed by the conclusions of the safety assessment studies, taking into account a number of significant non-radiological hazards. The paper also describes the preliminary dismantling operations performed in 2002 on concrete structures and decontamination of the hot cell walls. Significant experience feedback drawn up from these works is provided. Finally, is presented the ongoing work to be performed in the next eighteen months, until the final dismantling and decommissioning of Triton facility

Part of:
International conference on research reactor utilization, safety, decommissioning, fuel and waste management. Extended synopses

Additional details

Publishing Information

Imprint Title
International conference on research reactor utilization, safety, decommissioning, fuel and waste management. Extended synopses
Imprint Pagination
231 p.
Journal Page Range
p. 113
Report number
IAEA-CN--100

Conference

Title
International conference on research reactor utilization, safety, decommissioning, fuel and waste management
Dates
10-14 Nov 2003
Place
Santiago (Chile)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
35015576
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTAMINATION; FISSION PRODUCTS; IMPLEMENTATION; PLANNING; REACTOR DECOMMISSIONING; REACTOR DISMANTLING; REACTOR MATERIALS; SAFETY STANDARDS; SHIELDS; TRITON REACTOR
Descriptors DEC
DECOMMISSIONING; DEMOLITION; ENRICHED URANIUM REACTORS; ISOTOPES; MATERIALS; POOL TYPE REACTORS; RADIOACTIVE MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; STANDARDS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
IAEA-CN--100/75