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RRFM 2009 Transactions - European Nuclear Society

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LEU FUEL DISPOSITION AT WWR-M REACTOR AFTER<br />

IRRADIATION TEST<br />

KONOPLEV K.A., ORLOV S.P. AND ZAKHAROV A.S.<br />

Physics and Technology of Reactors Department<br />

Petersburg <strong>Nuclear</strong> Physics Institute<br />

PNPI, 188300, Gatchina, Russia<br />

ABSTRACT<br />

This presentation concern the disposition of two irradiated pin-type experimental<br />

fuel assemblies , which were tested in PNPI WWR-M reactor in support of<br />

demonstration of high-density fuel.<br />

The non-standard design of experimental fuel assemblies As requires a revision of<br />

procedures for storage and further utilization. One way is preparation for<br />

transportation to recycling plant together with standard fuel assemblies after<br />

cooling in wet spent fuel storage. Alternative is reloading to long-term spent fuel<br />

storage.<br />

Introduction<br />

The two pin-type experimental fuel assemblies were tested in PNPI WWR-M reactor in<br />

support of demonstration of high-density fuel for research reactors [1].<br />

Pin fuel is considered as alternative variant for replacing of standard fuel based on tube fuel<br />

elements. In view of conversion purpose serious limitation of thin-wall tubes is small volume<br />

of fuel meat. Pin fuel technology provides additional volume for fuel. At the same time pins<br />

demand fuel assembly casing. It means that small core grid pitch result in the loss of power<br />

density.<br />

The experimental fuel assemblies with LEU fuel were delivered by VNIINM [2]. One fuel<br />

assembly contains fuel elements based on UO 2 and other - UMo. Both types of fuel elements<br />

have an aluminium matrix and cladding. Each of fuel assemblies contains 37 pin elements<br />

(Fig.1) inside of hexagonal aluminium assembly casing .<br />

The volumetric contents of fission fraction in fuel elements in both cases are approximately<br />

identical (Table 1).<br />

No<br />

Fuel<br />

composition<br />

Average<br />

uranium-235<br />

load per FE,<br />

g<br />

Uranium<br />

concentration<br />

in fuel, g/ cm 3<br />

Length of<br />

fuel<br />

meat,<br />

mm<br />

Volume<br />

share of fuel<br />

component,<br />

%<br />

1 (U-Mo) + Al 2.54 5.3 500 33.9<br />

2 UO 2 + Al 1.30 2.7 500 31.0<br />

Table 1. Features of fuel<br />

Features of fuel assemblies are presented in Table 2.<br />

406 of 455

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