LI Dongsheng

He was Master of Science degree, graduated from nuclear reactor engineering and safety of Xi’an Jiaotong University in 1992.

Dongsheng Li is the Chief Engineer of Reactor Engineering and Safety Analysis Research Center, China Nuclear Power Technology Research Institute (CNPRI), China General Nuclear Power Group (CGN). He has been working at Nuclear Power Institute of China from 1978 to middle of 2009, and at China Nuclear Power Technology Research Institute since middle of 2009.

He focuses his attention on the nuclear reactor core research and design. He performed the nuclear reactor design for Qinshan and Ling’ao nuclear power plants, as well as the key technology research for advanced PWR. He was in charge of the in-core reload design, increasing fuel enrichment and long fuel cycle justification studies for the nuclear power plants, and now takes charge of a Chinese third generation PWR plant HPR1000.

SONG Danrong

PROFESSONAL EXPERIENCE

Nuclear Power Institute of China, Chief engineer office of research reactor
Chengdu, Sichuan (2001-2013) Chief Designer
1. Small and medium size reactor ACP100 overall design.
2. High-Tech project--Isotopic production reactor overall design.
3. Seawater desalination, low temperature nuclear heating plant feasibility study.
Nuclear Power Institute of China, Design and Research Sub-Institute
Chengdu, Sichuan (1991—2000) Engineer
1. Mechanical-electrical equipment for power plant design, Manufacturing surveillance, Components procurement, Installation & testing, In-factory acceptance, Shipping & transportation, On-site acceptance.
2. Design review documents related with systems of plant, Design review civil interface drawing related with building, Non-destructive examination contract package for vessel Procurement, Design change management.

GUIDEZ Joël

Engineer from “Ecole Centrale de Paris”, Joël Guidez has since 1973, worked in the field of nuclear reactors in France or in Europe, and especially on fast reactors and research reactors matters.
After seven years of engineering work for the sodium fast breeder reactor Superphenix, he becomes responsible of test and measurements in Phenix plant for five years, and then chief of a thermal hydraulic laboratory in CADARACHE research center. He is in 1993 head of the OSIRIS experimental reactor in Saclay. In 1997 Joël Guidez becomes responsible of the High Flux Reactor for the European commission in Petten. (Netherlands)
In 2002 he comes back as director of the French fast breeder reactor Phenix until the end of 2007 in Marcoule. Then he will be director of a direction of support to nuclear industry in Saclay.

His first European experience in Netherlands will be followed by another in 2009 in Germany, when he is nominated as CEA counselor in French embassy in Berlin.

In   2011, he came back on Saclay in the direction of nuclear energy. He published in 2012
a book on the experience feedback of the 35 years of Phenix operation, translated in English in 2013, published by the editor EDP SCIENCES and is writing in 2015 a book on Superphenix feedback experience.

M Joel Guidez is today CEA international expert, member of the CEA « haut commissaire.” operational committee, president of the section SFEN on reactor operation, member of the editorial committee of General Review on Nuclear. He represents France at the Reactor Safety Working Group in GIF and he is president of the GCFS: a team CEA /EDF/ AREVA working on safety of GENIV reactors.

Daniel Ingersoll

Dr. Daniel Ingersoll is Director of the Office of Research Collaborations for NuScale Power. He joined NuScale in January 2012 to coordinate and develop R&D partnerships between NuScale and universities, laboratories and industry. Prior to joining NuScale, he was Senior Program Manager for the Small Modular Reactors R&D Office at Oak Ridge National Laboratory where he served as National Technical Director for the U.S. Department of Energy’s Small Modular Reactor program. He also led the DOE Grid-Appropriate Reactor program and represented ORNL in the International Reactor Innovative and Secure (IRIS) consortium. During his 35 years at ORNL, he led several ORNL research organizations conducting radiation transport modeling, reactor shielding experiments and reactor physics analysis in support of advanced reactor development, advanced medical therapies, and defense applications.

Dr. Ingersoll received a BS degree in Physics from Miami University in 1973 and a PhD in Nuclear Engineering from the University of Illinois in 1977. He is a Fellow of the American Nuclear Society and former chairman of the ANS Radiation Protection and Shielding Division.