M. Salvatores

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At present Consultant in Reactor and Fuel Cycle Physics and part-time Scientific Advisor at the Idaho National Laboratory. Former Head of the Reactor and Fuel Cycle Physics Division at CEA-Cadarache. Subsequently named Research Director at that Institution.
Leader of international studies on innovative fuel cycles; presently performing basic research on nuclear data measurements, sensitivity and uncertainty analysis, advanced simulation experimental validation and on methods for innovative reactor systems.
Received the “Grand Prix Ampère” of the French Academy of Sciences and the American Nuclear Society (ANS) “E. Wigner” Award.
Fellow of the ANS and member of the International Nuclear Energy Academy.
Founder of the International Summer School in Reactor Physics “Frédéric Joliot/Otto Hahn”.
More than 250 peer-reviewed articles.

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Papers by M. Salvatores

Integral test of fission-product cross sections

Radiation Effects, 1986

... H. GRUPPELAAR, RJ HEIJBOER, AJ JANSSEN, HAJ VAN DER KAMP, Netherlands Energy Research Foundat... more

Special Invited Talk

Journal of Nuclear Science and Technology, 2000

Experimental and design experience with passive safety features of liquid metal reactors

Liquid metal cooled reactors (LMRs) have already been demonstrated to be robust machines. Many re... more Liquid metal cooled reactors (LMRs) have already been demonstrated to be robust machines. Many reactor designers now believe that it is possible to include in this technology sufficient passive safety that LMRs would be able to survive loss of flow, loss of heat sink, and transient overpower events, even if the plant protective system fails completely and do so without damage to the core. Early whole-core testing in Rapsodie, EBR-II. and FFTF indicate such designs may be possible. The operational safety testing program in EBR-II is demonstrating benign response of the reactor to a full range of controls failures. But additional testing is needed if transient core structural response under major accident conditions is to be properly understood. The proposed international Phase IIB passive safety tests in FFTF, being designed with a particular emphasis on providing, data to understand core bowing extremes, and further tests planned in EBR-II with processed IFR fuel should provide a su...

Data adjustment: a cautiously optimistic view for the improvement of design performance …

Trans. Am. Nucl. Soc

... Title, Data adjustment: a cautiously optimistic view for the improvement of design performanc... more

The EFTTRA experiment on irradiation of Am targets

Journal of Alloys and Compounds, 1998

ABSTRACT

A first approach to data needs and target accuracies for hybrid systems

Intermediate energy nuclear data: models and …, 1994

... 12-AJ Koning, NEA/NSC/DOC (92) 12. 13-AJ Koning, NEA/NSC/DOC (93) 6. 14-LN Usachev et al.&quo... more

Liquid Metal Cooled Fast Reactor

AtoZ, 2006

Analysis of nuclear power transmutation potential at equilibrium

Nuclear Science and Engineering - NUCL SCI ENG, 1996

A major issue to secure the development of nuclear energy in the future is the radioactive waste ... more A major issue to secure the development of nuclear energy in the future is the radioactive waste minimization, both inside the fuel cycle and in a deep geological storage. Most of the research activities have been devoted to assess the potential benefits of the so-called partitioning/transmutation technologies. The physical principles that provide an inherent minimization of the radioactive wastes is established. A new concept is introduced to characterize the radiotoxicity associated with various nuclei families in an equilibrium state. The analysis shows the potential of evolutionary nuclear systems, mostly based on known technologies and the potential of more futuristic systems, like accelerator-driven systems and the thorium fuel cycle.

Medium and Long Term Data Needs for Advanced Fission Reactors

Research Reports in Physics, 1992

Laser Measurements, Earth Moon Distance

Astronomy & Astrophysics, 1970

Accelerator-Driven Systems in Advanced Fuel Cycles

Nuclear Science, 2005

The GLOBPERT-1D Code

The CIAP-1D Code

The neutronic potential of nuclear power for long-term radioactivity risk reduction

Progress in Nuclear Energy, 1998

An analysis to evaluate the comparative neutronic transmutation potential of different nuclear po... more An analysis to evaluate the comparative neutronic transmutation potential of different nuclear power system (standard or advanced fission reactors and accelerator driven hybrids) is presented. The analysis is based on an evaluation of neutronic constraints for the reduction of both long-lived fission product toxicity and fuel waste toxicity integrated over the life of the nuclide families, taking into account the

Report on INL Activities for Uncertainty Reduction Analysis of FY11

ABSTRACT

Representativity of fuel and cladding material irradiations using a spallation neutron source

The relation of differential and integral experiments: An overview of accomplishments and new fields of investigation for fission reactors

Radiation Effects and Defects in Solids, 1986

The complementary role of integral experiments and differential data to meet fission reactor desi... more

Heterogeneity Effects on Neutron Self-Shielding Factors for Fast Reactors

Nuclear fuel cycle strategies including Partitioning and Transmutation

Nuclear Engineering and Design, 2005

The widespread concern about radioactive waste management has promoted interest during the last d... more The widespread concern about radioactive waste management has promoted interest during the last decade for the potential role of Partitioning and Transmutation strategies, in order to alleviate the burden on future deep geological repositories. The physics of transmutation allows to point-out preferential approaches, e.g., based on the use of a fast neutron spectrum. The practical implementation of Partitioning and Transmutation