You need JavaScript to view this

Licensing procedures and safety criteria for research reactors in France

Abstract

From the very beginning of the CEA up to now, a great deal of work has been devoted to the development and utilization of research reactors in France for the needs of fundamental and applied research, production of radioisotopes, and training. In recent years, new reactors were commissioned while others were decommissioned. Moreover some of the existing facilities underwent important modifications to comply with more severe safety criteria, increase the experimental capabilities or qualify new low-enrichment fuels for research reactors (Osiris and Isis). This paper summarizes the recent evolution of the French research reactor capacity, describes the licensing process, the main safety criteria which are taken into consideration, and associated safety research. At the end, a few considerations are given to the consequences of the Osiris core conversion. Safety of research reactors has been studied in detail and many improvements have been brought due to: implementation of a specific experimental program, and adaptation of safety principles and rules elaborated for power reactors. Research reactors in operation in France have been built within a 22 year period. Meanwhile, safety rules have been improved. Old reactors do not comply with all the new rules but modifications are continuously made: after analysis of  More>>
Authors:
Berry, J L; Lerouge, B [1] 
  1. Centre d'Etudes Nucleaires de Saclay (France)
Publication Date:
Aug 01, 1983
Product Type:
Conference
Report Number:
ANL/RERTR/TM-3; CONF-801144; INIS-XA-C-021
Resource Relation:
Conference: International meeting on development, fabrication, and application of Reduced Enrichment fuels for Research and Test Reactors (RERTR), Argonne, IL (United States), 12-14 Nov 1980; Other Information: 1 ref., 2 tabs; PBD: Aug 1983; Related Information: In: Proceedings of the international meeting on development, fabrication, and application of Reduced Enrichment fuels for Research and Test Reactors (RERTR). Base technology, 671 pages.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BURNUP; FUEL ELEMENTS; ISIS REACTOR; LICENSING PROCEDURES; OSIRIS REACTOR; PERFORMANCE TESTING; REACTOR COMMISSIONING; REACTOR CORES; REACTOR DECOMMISSIONING; REACTOR LICENSING; SAFETY STANDARDS
Sponsoring Organizations:
U.S. Department of Energy, Assistant Secretary for Nuclear Energy, Office of Spent Fuel Management and Reprocessing Systems (United States)
OSTI ID:
20571708
Research Organizations:
Argonne National Laboratory, Argonne, IL (United States)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
TRN: XA04C1542023715
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
page(s) 51-62
Announcement Date:

Citation Formats

Berry, J L, and Lerouge, B. Licensing procedures and safety criteria for research reactors in France. IAEA: N. p., 1983. Web.
Berry, J L, & Lerouge, B. Licensing procedures and safety criteria for research reactors in France. IAEA.
Berry, J L, and Lerouge, B. 1983. "Licensing procedures and safety criteria for research reactors in France." IAEA.
@misc{etde_20571708,
title = {Licensing procedures and safety criteria for research reactors in France}
author = {Berry, J L, and Lerouge, B}
abstractNote = {From the very beginning of the CEA up to now, a great deal of work has been devoted to the development and utilization of research reactors in France for the needs of fundamental and applied research, production of radioisotopes, and training. In recent years, new reactors were commissioned while others were decommissioned. Moreover some of the existing facilities underwent important modifications to comply with more severe safety criteria, increase the experimental capabilities or qualify new low-enrichment fuels for research reactors (Osiris and Isis). This paper summarizes the recent evolution of the French research reactor capacity, describes the licensing process, the main safety criteria which are taken into consideration, and associated safety research. At the end, a few considerations are given to the consequences of the Osiris core conversion. Safety of research reactors has been studied in detail and many improvements have been brought due to: implementation of a specific experimental program, and adaptation of safety principles and rules elaborated for power reactors. Research reactors in operation in France have been built within a 22 year period. Meanwhile, safety rules have been improved. Old reactors do not comply with all the new rules but modifications are continuously made: after analysis of incidents, when replacement of equipment has to be carried out, when an important modification (fuel conversion for example) is decided upon.}
place = {IAEA}
year = {1983}
month = {Aug}
}