EU 3 Physics of Nuclear Reactors GEN - 5PUGPRN4

Goal(s)

MC Simulations
Get some first expertise in using a Monte Carlo code for simulation of neutron transport, to be used in typical nuclear reactor core studies

Fuel Cycle
The management of the nuclear wastes due to nuclear energy production is a key issue of this industry. The goals of these lectures are to introduce the fundamental notions to then present the physics of the transmutation and incineration processes, together with the behavior of current and future nuclear reactor technologies while introducing minor actinides in their fuel; finally to discuss the available options to reduce the risks linked to the long-lived radioactive wastes.

Content(s)

MC Simulations
Chapter 1 : getting familiar with the code
Chapter 2 : criticality calculations
Chapter 3 : calculation of fluxes and reaction rates
Chapter 4 : from cell calculations to full core calculations (and beyond)
Will be completed by radioprotection calculations

Fuel Cycle
Part 1 - Introduction: Fuel Cycles
• Radioactivity and radioprotection
• Nuclear: classification and production
• The fission products
• The transuranic elements: plutonium and minor actinides
Part 2 - The physics of transmutation and incinération
• Case of the fission products
• Case of the plutonium
• Case of the minor actinides (Np, Am, Cm)
Part 3 - R&D activities towards future reactor concepts
(Generation 4 reactors and Accelerator Driven Systems)

Nuclear physics and reactor physics

Test

Additional Information