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Neutronic analysis concerning the utilization of mixed U N-Pu N nitride fuel for fast reactors; Analise neutronica concernente a utilizacao de combustivel nitreto de uranio/plutonio em reatores a neutrons rapidos

Technical Report:

Abstract

Neutronic behavior of mixed UN-PuN nitride fuel in substitution of the mixed oxide U O{sub 2} - Pu O{sub 2} for fast reactors is discussed with focus on Super Phenix I. Characteristics parameters of both cores are calculated and compared and the results presented show a great advantage for the nitride fuel, pointing out a larger performance of fuel elements in the core and an effective reduction of reactivity loss during the cycle. (author).
Publication Date:
Aug 01, 1991
Product Type:
Technical Report
Report Number:
IEN-26/91
Reference Number:
SCA: 210500; PA: AIX-24:002555; SN: 93000913311
Resource Relation:
Other Information: PBD: Aug 1991
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; SUPER PHENIX REACTOR; FUEL ELEMENTS; FUEL CYCLE; PLUTONIUM NITRIDES; REACTOR CORES; URANIUM NITRIDES; 210500; POWER REACTORS, BREEDING
OSTI ID:
10108842
Research Organizations:
Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil)
Country of Origin:
Brazil
Language:
Portuguese
Other Identifying Numbers:
Other: ON: DE93609485; TRN: BR9230398002555
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
[26] p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Renke, C A.C., Batista, J L, Waintraub, M, Santos Bastos, W dos, and Brito Aghina, L.O. de. Neutronic analysis concerning the utilization of mixed U N-Pu N nitride fuel for fast reactors; Analise neutronica concernente a utilizacao de combustivel nitreto de uranio/plutonio em reatores a neutrons rapidos. Brazil: N. p., 1991. Web.
Renke, C A.C., Batista, J L, Waintraub, M, Santos Bastos, W dos, & Brito Aghina, L.O. de. Neutronic analysis concerning the utilization of mixed U N-Pu N nitride fuel for fast reactors; Analise neutronica concernente a utilizacao de combustivel nitreto de uranio/plutonio em reatores a neutrons rapidos. Brazil.
Renke, C A.C., Batista, J L, Waintraub, M, Santos Bastos, W dos, and Brito Aghina, L.O. de. 1991. "Neutronic analysis concerning the utilization of mixed U N-Pu N nitride fuel for fast reactors; Analise neutronica concernente a utilizacao de combustivel nitreto de uranio/plutonio em reatores a neutrons rapidos." Brazil.
@misc{etde_10108842,
title = {Neutronic analysis concerning the utilization of mixed U N-Pu N nitride fuel for fast reactors; Analise neutronica concernente a utilizacao de combustivel nitreto de uranio/plutonio em reatores a neutrons rapidos}
author = {Renke, C A.C., Batista, J L, Waintraub, M, Santos Bastos, W dos, and Brito Aghina, L.O. de}
abstractNote = {Neutronic behavior of mixed UN-PuN nitride fuel in substitution of the mixed oxide U O{sub 2} - Pu O{sub 2} for fast reactors is discussed with focus on Super Phenix I. Characteristics parameters of both cores are calculated and compared and the results presented show a great advantage for the nitride fuel, pointing out a larger performance of fuel elements in the core and an effective reduction of reactivity loss during the cycle. (author).}
place = {Brazil}
year = {1991}
month = {Aug}
}