Use of metallic uranium in the power channels of uranium-graphite reactors

Journal Article · Fri Jun 01 04:00:00 EDT 1973 · At. Energ. (USSR), v. 34, no. 6, pp. 479-481

OSTI ID:4411625

Zhirnov, A D; Sirotkin, A P; Bryunin, S V; Pushkarev, V I; Runin, V I

It was established experimentally that in a fuel rod with 5% free internal volume it is possible to attain a fuel burnup of 15,00020,000 MWd/ton of U. Porosity of the fuel, thickness of fuel element cladding (0.65 and 0.9 mm) and uranium enrichment (1 to 2.4%) were varied in calculating whether the costs of using metal in a reactor are comparable with using uranium dioxide as a fuel. With the use of 0, 10 and 15% porosities the metal exceeded the effective density of UO/sub 2/ in a lattice arrangement by factors of 2, 1.82 and 1.71 respectively. The fuel expense increases with increasing burnup because of the necessity of higher fuel enrichment at startup. The plant load use was 0.80. Normal capital return was 0.12. Various burnups are given as a fuanction of fuel enrichment for UO/sub 2/ and metal U having 15% free volume. With the use of metallic uranium it is shown that costs are minimal at burnups of ~11,500 MWd/ton of U for a solid fuel rod, ~12,500 MWd/ton of U with 10% porosity in the fuel rod, and ~13,000 MWd/ ton of U at 15% porosity. The initial enrichments in these three cases were 1.18, 1.21 and 1.23% respectively. For UO/sub 2/ the minimum costs are encountered at burnups of 20,000-22,000 MWd/ton of U at initial /sup 235/ enrichments of 1.8-1.9%. However, the metal possesses some advantages over the oxide for use in power reactors, and its further development is recommended. (SJR)

• Research Organization: Originating Research Org. not identified
• NSA Number: NSA-29-004562
• OSTI ID: 4411625
• Journal Information: At. Energ. (USSR), v. 34, no. 6, pp. 479-481, Journal Name: At. Energ. (USSR), v. 34, no. 6, pp. 479-481; ISSN AENGA
• Country of Publication: Country unknown/Code not available
• Language: Russian

Related Subjects

*FUEL CYCLE-- COST
*GRAPHITE MODERATED REACTORS-- FUEL CYCLE
*POWER REACTORS-- FUEL CYCLE
BURNUP
COMPARATIVE EVALUATIONS
ENRICHED URANIUM
N79600* --Reactors--Reactor Fuel Cycle Economics
POROSITY
URANIUM
URANIUM DIOXIDE