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Title: FFTF fuel rotation for extended burnup

Abstract

The standard driver fuel assemblies for the Fast Flux Test Facility (FFTF) reactor are hexagonally shaped components, 11.976 cm (4.715 in.) across outside load pad flats and 3.66 m (12 ft) long. The assembly is composed of a bundle of 217 fuel pins, 0.584-cm (0.230-in.) o.d., containing mixed oxide (PuO/sub 2/-UO/sub 2/) pellets; a surrounding duct and lower and upper end hardware. The hexagonally shaped FFTF driver fuel assembly can be positioned within a given core location in any one of six possible orientations. This paper describes how rotation or reorientation of outer fuel in the core provides additional margin for extended burnup. The implementation of this rotation plan is now well under way at the FFTF. Twenty-two driver fuel assemblies in rows 4, 5, and 6 were rotated during the cycle 7 refueling in August of 1985. The projected average peak pellet burnup reduction for these fuel assemblies was 8% as shown in Table I. FFTF Core Management plans to continue rotation of approx.20 fuel assemblies per year - amounting to an annual cost savings of approx.$400,000, based on saving the equivalent of one to two assemblies per year.

Authors:
Publication Date:
Research Org.:
Westinghouse Hanford Co., Richland, WA
OSTI Identifier:
7124692
Report Number(s):
CONF-861102-
Journal ID: CODEN: TANSA
Resource Type:
Conference
Journal Name:
Trans. Am. Nucl. Soc.; (United States)
Additional Journal Information:
Journal Volume: 53; Conference: American Nuclear Society and Atomic Industrial Forum joint meeting, Washington, DC, USA, 16 Nov 1986
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; FFTF REACTOR; FUEL MANAGEMENT; BURNUP; DEFORMATION; DESIGN; FUEL ASSEMBLIES; MODIFICATIONS; POWER DISTRIBUTION; REACTOR CORES; SERVICE LIFE; EPITHERMAL REACTORS; FAST REACTORS; LIQUID METAL COOLED REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; TEST REACTORS; 220600* - Nuclear Reactor Technology- Research, Test & Experimental Reactors; 210500 - Power Reactors, Breeding

Citation Formats

Bennett, C L. FFTF fuel rotation for extended burnup. United States: N. p., 1986. Web.
Bennett, C L. FFTF fuel rotation for extended burnup. United States.
Bennett, C L. 1986. "FFTF fuel rotation for extended burnup". United States.
@article{osti_7124692,
title = {FFTF fuel rotation for extended burnup},
author = {Bennett, C L},
abstractNote = {The standard driver fuel assemblies for the Fast Flux Test Facility (FFTF) reactor are hexagonally shaped components, 11.976 cm (4.715 in.) across outside load pad flats and 3.66 m (12 ft) long. The assembly is composed of a bundle of 217 fuel pins, 0.584-cm (0.230-in.) o.d., containing mixed oxide (PuO/sub 2/-UO/sub 2/) pellets; a surrounding duct and lower and upper end hardware. The hexagonally shaped FFTF driver fuel assembly can be positioned within a given core location in any one of six possible orientations. This paper describes how rotation or reorientation of outer fuel in the core provides additional margin for extended burnup. The implementation of this rotation plan is now well under way at the FFTF. Twenty-two driver fuel assemblies in rows 4, 5, and 6 were rotated during the cycle 7 refueling in August of 1985. The projected average peak pellet burnup reduction for these fuel assemblies was 8% as shown in Table I. FFTF Core Management plans to continue rotation of approx.20 fuel assemblies per year - amounting to an annual cost savings of approx.$400,000, based on saving the equivalent of one to two assemblies per year.},
doi = {},
url = {https://www.osti.gov/biblio/7124692}, journal = {Trans. Am. Nucl. Soc.; (United States)},
number = ,
volume = 53,
place = {United States},
year = {Wed Jan 01 00:00:00 EST 1986},
month = {Wed Jan 01 00:00:00 EST 1986}
}

Conference:
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