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Application of gel-Co-conversion for TRU (Pu, Np, Am) fuel and target preparation

Technical Report:

Abstract

In the fabrication of fuel containing transuranium (TRU) elements, flow sheets and techniques which allow a shielded and/or remote fabrication will probably need to be applied. One approach, which has been demonstrated on the laboratory and semi prototype scale, is the wet fabrication route of coprecipitation of the matrix element uranium mixed with plutonium to form dense spherical particles or to produce hybrid pellets made from pressed gel microspheres. The ceramic material produced holds the TRU-elements homogeneously distributed in the matrix. In conjunction with the Departement d`Etudes des Combustibles of the French Commissariat a l`Energie Atomique (CEA-DEC) in Cadarache, the Paul Scherrer Institut (PSI) in Switzerland is further developing a mixed nitride ceramic and mixed oxide with high concentrations (up to 50%) of plutonium with the aim of a joint irradiation test of transuranium elements in the French PHENIX reactor. 6 refs., 3 figs., 3 tabs.
Authors:
Prunier, C; Warin, D; Bauer, M; [1]  Ledergerber, G; Ingold, F; Stratton, R W; Alder, H P [2] 
  1. CEA Centre d`Etudes de Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. d`Etudes des Combustibles
  2. Paul Scherrer Inst. (PSI), Villigen (Switzerland)
Publication Date:
Dec 01, 1993
Product Type:
Technical Report
Report Number:
CEA-CONF-11608; CONF-930913-
Reference Number:
SCA: 210500; PA: AIX-25:003379; EDB-94:012427; ERA-19:003621; NTS-94:014080; SN: 93001120648
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:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; MIXED NITRIDE FUELS; PLUTONIUM NITRIDES; PHENIX REACTOR; ACTINIDES; CEA CADARACHE; COORDINATED RESEARCH PROGRAMS; COPRECIPITATION; EXPERIMENTAL DATA; FUEL PELLETS; GELATION; SINTERED MATERIALS; 210500; POWER REACTORS, BREEDING
OSTI ID:
10109685
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: DE94609289; TRN: FR9303876003379
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
FRN
Size:
8 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Prunier, C, Warin, D, Bauer, M, Ledergerber, G, Ingold, F, Stratton, R W, and Alder, H P. Application of gel-Co-conversion for TRU (Pu, Np, Am) fuel and target preparation. France: N. p., 1993. Web.
Prunier, C, Warin, D, Bauer, M, Ledergerber, G, Ingold, F, Stratton, R W, & Alder, H P. Application of gel-Co-conversion for TRU (Pu, Np, Am) fuel and target preparation. France.
Prunier, C, Warin, D, Bauer, M, Ledergerber, G, Ingold, F, Stratton, R W, and Alder, H P. 1993. "Application of gel-Co-conversion for TRU (Pu, Np, Am) fuel and target preparation." France.
@misc{etde_10109685,
title = {Application of gel-Co-conversion for TRU (Pu, Np, Am) fuel and target preparation}
author = {Prunier, C, Warin, D, Bauer, M, Ledergerber, G, Ingold, F, Stratton, R W, and Alder, H P}
abstractNote = {In the fabrication of fuel containing transuranium (TRU) elements, flow sheets and techniques which allow a shielded and/or remote fabrication will probably need to be applied. One approach, which has been demonstrated on the laboratory and semi prototype scale, is the wet fabrication route of coprecipitation of the matrix element uranium mixed with plutonium to form dense spherical particles or to produce hybrid pellets made from pressed gel microspheres. The ceramic material produced holds the TRU-elements homogeneously distributed in the matrix. In conjunction with the Departement d`Etudes des Combustibles of the French Commissariat a l`Energie Atomique (CEA-DEC) in Cadarache, the Paul Scherrer Institut (PSI) in Switzerland is further developing a mixed nitride ceramic and mixed oxide with high concentrations (up to 50%) of plutonium with the aim of a joint irradiation test of transuranium elements in the French PHENIX reactor. 6 refs., 3 figs., 3 tabs.}
place = {France}
year = {1993}
month = {Dec}
}