Published 1998 | Version v1
Book

Characteristics of upper-bound fuel rods for criticality studies of fresh and spent fuel assembly transport casks

  • 1. CEA Fontenay-aux-Roses, 92 (France). Dept. de Prevention et d'Etude des Accidents

Description

The reactivity of light water reactor fresh and spent fuel assemblies depends greatly on the geometrical characteristics of the fuel rods of which they consist, as well as on their moderation. As concerns the geometrical characteristics, each type of fuel rod can be accurately identified on the basis of the diameter of the pellet, the thickness of the cladding and the outside diameter of the cladding. The values of these three parameters do, however, vary slightly relative to their nominal values, as a result of not only dimensional tolerance limits or changes caused by irradiation. These tolerance limits are generally mentioned explicitly or implicitly in the descriptions of the permitted contents in the certificates of approval, whereas the criticality studies on which they are based frequently cover only a very small number of fuel rods whose geometrical parameters do not vary. This means that these parameters constitute upper bounds relative to those of the certificates in terms of reactivity, hence the importance of a general method for establishing the set of upper bound parameters. (authors)

Part of:
Packaging and transportation of radioactive materials

Additional details

Publishing Information

Publisher
Societe Francaise d'Energie Nucleaire - SFEN
Imprint Place
Paris (France)
Imprint Title
Packaging and transportation of radioactive materials
Imprint Pagination
(v.1) [482 p.]
Journal Page Range
p. 224-230

Conference

Title
12. Conference on Packaging and Transportation of Radioactive Materials
Dates
10-15 May 1998
Place
Paris (France)

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
31003799
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
A CODES; CRITICALITY; FUEL ASSEMBLIES; FUEL RODS; PWR TYPE REACTORS
Descriptors DEC
COMPUTER CODES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
3 refs.