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Performance and fuel cycle cost analysis of one Janus 30 conceptual design for several fuel element design options

Abstract

The performance and fuel cycle costs for a 25 MW, JANUS 30 reactor conceptual design by INTERATOM, Federal Republic of Germany, for BATAN, Republic of Indonesia have been studied using 19.75% enriched uranium in four fuel element design options. All of these fuel element designs have either been proposed by INTERATOM for various reactors or are currently in use with 93% enriched uranium in reactors in the Federal Republic of Germany. Aluminide, oxide, and silicide fuels were studied for selected designs using the range of uranium densities that are either currently qualified or are being developed and demonstrated internationally. These uranium densities include 1.7-2.3 g/cm{sup 3} in aluminide fuel, 1.7-3.2 g/cm{sup 3} in oxide fuel, and 2.9-6.8 g/cm{sup 3} in silicide fuel. As of November 1982) both the aluminide and the oxide fuels with about 1.7 g U/cm{sup 3} are considered to be fully-proven for licensing purposes. Irradiation screening and proof testing of fuels with uranium densities greater than 1.7 g/cm{sup 3} are currently in progress, and these tests need to be completed in order to obtain licensing authorization for routine reactor use. To assess the long-term fuel adaptation strategy as well as the present fuel acceptance, reactor performance and  More>>
Authors:
Nurdin, Martias; [1]  Matos, J E; Freese, K E [2] 
  1. Research Centre for Nuclear Techniques, National Atomic Energy Agency (Indonesia)
  2. RERTR Program, Argonne National Laboratory (United States)
Publication Date:
Sep 01, 1983
Product Type:
Conference
Report Number:
ANL/RERTR/TM-4; CONF-821155; INIS-XA-C-020
Resource Relation:
Conference: International meeting on research and test reactor core conversions from HEU to LEU fuels, Argonne, IL (United States), 8-10 Nov 1982; Other Information: 4 refs, 8 figs, 5 tabs; PBD: Sep 1983; Related Information: In: Proceedings of the international meeting on research and test reactor core conversions from HEU to LEU fuels, by Travelli, A. [Argonne National Laboratory, Argonne, IL (United States)], 723 pages.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ALUMINIUM COMPOUNDS; CLADDING; ECONOMICS; FUEL CYCLE; FUEL ELEMENTS; HIGHLY ENRICHED URANIUM; JANUS REACTOR; REACTIVITY COEFFICIENTS; REACTOR LICENSING; SAFETY ANALYSIS; URANIUM OXIDES; URANIUM SILICIDES
Sponsoring Organizations:
US Department of Energy, Washington, DC (United States)
OSTI ID:
20596967
Research Organizations:
Argonne National Laboratory, Argonne, IL (United States); University of Chicago, Chicago (United States)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Other: Contract W-31-109-Eng-38; TRN: XA04C1533043351
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
page(s) 580-598
Announcement Date:

Citation Formats

Nurdin, Martias, Matos, J E, and Freese, K E. Performance and fuel cycle cost analysis of one Janus 30 conceptual design for several fuel element design options. IAEA: N. p., 1983. Web.
Nurdin, Martias, Matos, J E, & Freese, K E. Performance and fuel cycle cost analysis of one Janus 30 conceptual design for several fuel element design options. IAEA.
Nurdin, Martias, Matos, J E, and Freese, K E. 1983. "Performance and fuel cycle cost analysis of one Janus 30 conceptual design for several fuel element design options." IAEA.
@misc{etde_20596967,
title = {Performance and fuel cycle cost analysis of one Janus 30 conceptual design for several fuel element design options}
author = {Nurdin, Martias, Matos, J E, and Freese, K E}
abstractNote = {The performance and fuel cycle costs for a 25 MW, JANUS 30 reactor conceptual design by INTERATOM, Federal Republic of Germany, for BATAN, Republic of Indonesia have been studied using 19.75% enriched uranium in four fuel element design options. All of these fuel element designs have either been proposed by INTERATOM for various reactors or are currently in use with 93% enriched uranium in reactors in the Federal Republic of Germany. Aluminide, oxide, and silicide fuels were studied for selected designs using the range of uranium densities that are either currently qualified or are being developed and demonstrated internationally. These uranium densities include 1.7-2.3 g/cm{sup 3} in aluminide fuel, 1.7-3.2 g/cm{sup 3} in oxide fuel, and 2.9-6.8 g/cm{sup 3} in silicide fuel. As of November 1982) both the aluminide and the oxide fuels with about 1.7 g U/cm{sup 3} are considered to be fully-proven for licensing purposes. Irradiation screening and proof testing of fuels with uranium densities greater than 1.7 g/cm{sup 3} are currently in progress, and these tests need to be completed in order to obtain licensing authorization for routine reactor use. To assess the long-term fuel adaptation strategy as well as the present fuel acceptance, reactor performance and annual fuel cycle costs were computed for seventeen cases based on a representative end-of-cycle excess reactivity and duty factor. In addition, a study was made to provide data for evaluating the trade-off between the increased safety associated with thicker cladding and the economic penalty due to increased fuel consumption. (author)}
place = {IAEA}
year = {1983}
month = {Sep}
}