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A study of the transmutation performance of externally driven sub-critical assemblies

Technical Report:

Abstract

For transmutation systems based on externally driven sub-critical assemblies with a fast neutron spectrum, there is an incentive to expose the actinides directly to the source neutrons, since these neutrons have higher energies than the fission neutrons. To evaluate the transmutation effectiveness of such systems, a parameter study based on the PHOENIX system, i.e. a sodium-cooled system with a minor actinide (MA) oxide fuelled target was performed. An interesting result is that the high-energy source neutrons give rise to a 20-25% increase in the fission-to-capture ratio of the important (fissionable) nuclides. Moreover, the performance of such a system can be further improved by substituting the oxide fuel by metal fuel and by reducing the volume fraction of steel in the target. Replacing the liquid sodium coolant by liquid lead has only a small effect on the fission-to-capture ratio, however, for a given proton current, the neutron production in the target increases. 17 refs., 5 tabs., 2 figs.
Authors:
Kadi, Y; [1]  Wydler, P; Caro, M; Pelloni, S; Ahmed, S [2] 
  1. CEA Centre d`Etudes de Cadarache, 13 - Saint-Paul-lez-Durance (France). Direction des Reacteurs Nucleaires
  2. Paul Scherrer Inst. (PSI), Villigen (Switzerland)
Publication Date:
Dec 01, 1993
Product Type:
Technical Report
Report Number:
CEA-CONF-11600; CONF-930913-
Reference Number:
SCA: 220600; PA: AIX-25:003391; EDB-94:012599; ERA-19:003771; NTS-94:014081; SN: 93001120658
Resource Relation:
Conference: Global `93: future nuclear systems - emerging fuel cycles and waste disposal options,Seattle, WA (United States),12-17 Sep 1993; Other Information: PBD: 1993
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; ACTINIDES; TRANSMUTATION; AMERICIUM 241; AMERICIUM 243; COMPUTER CODES; CURIUM 244; EXPERIMENTAL DATA; NEPTUNIUM 237; PLUTONIUM 248; SODIUM COOLED REACTORS; SUBCRITICAL ASSEMBLIES; 220600; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS
OSTI ID:
10109691
Research Organizations:
CEA Centre d`Etudes de Cadarache, 13 - Saint-Paul-lez-Durance (France). Direction des Reacteurs Nucleaires
Country of Origin:
France
Language:
English
Other Identifying Numbers:
Other: ON: DE94609292; TRN: FR9303868003391
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
FRN
Size:
12 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Kadi, Y, Wydler, P, Caro, M, Pelloni, S, and Ahmed, S. A study of the transmutation performance of externally driven sub-critical assemblies. France: N. p., 1993. Web.
Kadi, Y, Wydler, P, Caro, M, Pelloni, S, & Ahmed, S. A study of the transmutation performance of externally driven sub-critical assemblies. France.
Kadi, Y, Wydler, P, Caro, M, Pelloni, S, and Ahmed, S. 1993. "A study of the transmutation performance of externally driven sub-critical assemblies." France.
@misc{etde_10109691,
title = {A study of the transmutation performance of externally driven sub-critical assemblies}
author = {Kadi, Y, Wydler, P, Caro, M, Pelloni, S, and Ahmed, S}
abstractNote = {For transmutation systems based on externally driven sub-critical assemblies with a fast neutron spectrum, there is an incentive to expose the actinides directly to the source neutrons, since these neutrons have higher energies than the fission neutrons. To evaluate the transmutation effectiveness of such systems, a parameter study based on the PHOENIX system, i.e. a sodium-cooled system with a minor actinide (MA) oxide fuelled target was performed. An interesting result is that the high-energy source neutrons give rise to a 20-25% increase in the fission-to-capture ratio of the important (fissionable) nuclides. Moreover, the performance of such a system can be further improved by substituting the oxide fuel by metal fuel and by reducing the volume fraction of steel in the target. Replacing the liquid sodium coolant by liquid lead has only a small effect on the fission-to-capture ratio, however, for a given proton current, the neutron production in the target increases. 17 refs., 5 tabs., 2 figs.}
place = {France}
year = {1993}
month = {Dec}
}