Published 2019 | Version v1
Miscellaneous Restricted

Development of an ISO standard related to geometrical dimensions for subcriticality control

  • 1. Orano Projects, 1 rue des Herons, 78180 Montigny-le-Bretonneux (France)
  • 2. IRSN, B.P. 17 - 92262 Fontenay-aux-Roses Cedex (France)
  • 3. Orano La Hague, 50440 Beaumont-Hague (France)
  • 4. Framatome, 10 rue Juliette Recamier, 69006 Lyon (France)
  • 5. CEA, 91191 Gif sur Yvette (France)
  • 6. ORNL, Knoxville, TN (United States)

Description

Nuclear criticality safety is often based on requirements limiting geometrical dimensions. This is usually expressed as maximal dimensions for process equipment containing fissile material (e.g. maximal diameter of columns, maximal height of a stack...) or minimal dimensions for interactions (e.g. storage pitch) or neutron absorber dimensions (e.g. thickness of a cadmium sheet). These limits are derived from nuclear criticality safety calculations and assessment. The nuclear criticality safety specialist needs to deal with different topics: how to avoid an intractable amount of limits while maintaining an adequate safety level, how to comply with the requirements, what should be compared. In this context, an ISO (International Organization for Standardization) standard has been developed (ISO 21391) by Subcommittee SC 5 (Nuclear installations, processes and technologies) of Technical Committee ISO/TC 85 (Nuclear energy, nuclear technologies, and radiological protection), in order to provide guidance, requirements and recommendations related to the determination of the relevant dimensions to be ensured on the one hand, and to the comparison between actual dimensions and subcriticality dimensions on the other hand. This paper presents the main items, with examples illustrating how to avoid unnecessary complexities, why some dimensions are better suited for controls, how to deal with aging effects and deformations due to aggressions to be taken into account. These examples are analyzed either from the point of view of the design engineer or of the operation team. It also briefly touches which topics are commonly linked to the geometrical dimensions (e.g. neutron absorber content). (authors)

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Additional details

Publishing Information

Imprint Pagination
10 p.
Report number
INIS-FR--21-0196

Conference

Title
11. international conference on nuclear criticality safety
Acronym
ICNC 2019
Dates
15-20 Sep 2019
Place
Paris (France)

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
52011572
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CALCULATION METHODS; CRITICALITY; ISO; RECOMMENDATIONS; REGULATIONS; SAFETY MARGINS; TOLERANCE
Descriptors DEC
INTERNATIONAL ORGANIZATIONS; LAWS

Optional Information

Notes
4 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses