This project is conceived to improve your knowledge
in fundamentals of nuclear reactor design,
as taught in the four chapters studied in class:
3) graphite-moderated reactors
4) reactors with reduced moderation,
by working on some recent and accessible research.
Neutronic and Thermal-Hydraulic Analyses of
Hydride-Fueled PWR Cores
(selected from a special issue of the Nuclear Engineering and Design journal,
with contributions of Berkeley and MIT's Departments of Nuclear Engineering)
Nuclear Design, How To ?
Teacher and contact : Alexis Nuttin
Authors : E. Greenspan (Berkeley) & N. Todreas (MIT)
4 subjects (the 4 parts of the 2 articles at bottom of this page)
All different, but on the same topic of hydride-fueled PWRs
Each subject is studied and presented by only one group
Understanding and synthesis work in group
During our brainstorming sessions and outside
Questions about precise issues to ask by e-mail (to authors ideally)
Send documents by e-mail before october 19
Slides in pdf, w/o animation (4 max. per person)
Abstract of about 800 words (2 pages max.)
Pedagogic & synthetic presentation ("best way to learn is to teach")
10-minute presentation per group (1/4h max.)
10-minute Q&A session (from the other groups and the professor)
Unique session (october 23)
article 1 (PWR & neutron), part a (1. to 4.) : methodology and first results
Louis, Paulo
article 1 (PWR & neutron), part b (5. to 6.) : safety optimization with burnable poisons
Hanna, Lanlan, Oguz
Aleksandra, Jakub, Neil
article 2 (PWR & thermal), part b (5. to 7.) : results and maximum achievable power
Matthew, Rafał, Warren
Thanks to all for the nice game we've had with Le Zoo des Systèmes