Inert matrix fuel strategies in the nuclear fuel cycle: the status of the initiative efforts at the 8th Inert Matrix Fuel Workshop

2003 ◽  
Vol 319 ◽  
pp. 1-5 ◽  
Author(s):  
C. Degueldre ◽  
T. Yamashita
Keyword(s):  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
Inert Matrix Fuel ◽  
Inert Matrix ◽  
The Status

Inert matrix fuel — A new challenge for material technology in the nuclear fuel cycle

2001 ◽  
Vol 7 (2) ◽  
pp. 159-164 ◽  
Author(s):  
Young-Woo Lee ◽  
Chang Young Joung ◽  
Si Hyung Kim ◽  
Sang-Chul Lee
Keyword(s):  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
Material Technology ◽  
Inert Matrix Fuel ◽  
Inert Matrix

scholarly journals Wastes Management Through Transmutation in an ADS Reactor

2008 ◽  
Vol 2008 ◽  
pp. 1-6 ◽  
Author(s):  
Barbara Calgaro ◽  
Barbara Vezzoni ◽  
Nicola Cerullo ◽  
Giuseppe Forasassi ◽  
Bernard Verboomen
Keyword(s):  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
Industrial Scale ◽  
Minor Actinides ◽  
Preliminary Evaluation ◽  
Inert Matrix Fuel ◽  
Inert Matrix ◽  
Core Content ◽  
Main Challenge

The main challenge in nuclear fuel cycle closure is the reduction of the potential radiotoxicity, or of the time in which that possible hazard really exists. Probably, the transmutation of minor actinides with fast fission processes is the most effective answer. This work, performed in (Belgium) and DIMNP Pisa University, is focused on preliminary evaluation of industrial scale ADS (400 MWth, 2.5 mA) burning capability. An inert matrix fuel of minor actinides, 50% vol. MgO and 50% vol. (Pu,Np,Am,Cm), core content, with 150 GWd/ton discharge burn up, is used. The calculations were performed using ALEPH-1.1.2, MCNPX-2.5.0, and ORIGEN2.2. codes.

Aluminosilicate-Phosphate Model of Polyphase Matrices for Immobilization of Sr-Cs-fractions of Nuclear Fuel Cycle HLW

2013 ◽  
Vol 7 (3) ◽  
pp. 209-219 ◽  
Author(s):  
R. Bogdanov ◽  
R. Kuznetsov ◽  
V. Epimahov ◽  
A. Titov ◽  
E. Prudnikov
Keyword(s):  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle

A family of uranyl oxide hydrate phases with bivalent cations [MII(H2O)4][(UO2)3O3(OH)2]·H2O (MII – Mn, Co, Ni, Zn): synthesis, characterization and chemical stability in aqueous solutions

2021 ◽  
Author(s):  
Nikolay G. Chernorukov ◽  
Oxana V. Nipruk ◽  
Kseniya A. Klinshova ◽  
Olga N. Tumaeva ◽  
Dmitry V. Sokolov
Keyword(s):  
Aqueous Solutions ◽  
Nuclear Fuel ◽  
Chemical Stability ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
Oxide Hydrate ◽  
Uranium Compounds ◽  
Bivalent Cations

A series of new uranium compounds [MII(H2O)3][(UO2)3O3(OH)2]·2H2O (MII – Mn, Co, Ni, Zn) were synthesized for binding radionuclides in the environment and nuclear fuel cycle.

Comparison of nuclear data uncertainties with other nuclear fuel cycle uncertainty sources

2021 ◽  
Author(s):  
Aris V. Skarbeli ◽  
Rubén Eusebio‐Yebra ◽  
Pablo Romojaro ◽  
Francisco Álvarez‐Velarde ◽  
Daniel Cano‐Ott
Keyword(s):  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Data ◽  
Nuclear Fuel Cycle ◽  
Uncertainty Sources

Massimo Salvatores’ seminal ideas and comprehensive views on nuclear fuel cycle studies

2021 ◽  
Vol 157 ◽  
pp. 108223
Author(s):  
Concetta Fazio ◽  
Fabrizio Gabrielli ◽  
Andrei Rineiski ◽  
Barbara Vezzoni
Keyword(s):  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle

scholarly journals Progress in Uranium Chemistry: Driving Advances in Front-End Nuclear Fuel Cycle Forensics

2021 ◽  
Author(s):  
Kevin J. Pastoor ◽  
R. Scott Kemp ◽  
Mark P. Jensen ◽  
Jenifer C. Shafer
Keyword(s):  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
Front End
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