Description
Experimental Nuclear Reactor Analysis
Theory, Numerical Models and Experimental Analysis
Woodhead Publishing Series in Energy Series
Coordinators: Cammi Antonio, Lorenzi Stefano
Language: EnglishSubjects for Experimental Nuclear Reactor Analysis:
Keywords
Nuclear reactors; nuclear reactor analysis; experimental nuclear reactors; TRIGA reactors; nuclear kinetics; dynamics of nuclear reactors; thermal-hydraulics; reactor physics; numerical models for nuclear reactor simulation; fission; neutron physics; research reactors; kinetics; computational models; reactivity; control mechanisms; reactor stabilities; reactor instabilities; reactor period method; rod drop method; subcritical core configuration method; void coefficient; fuel temperature coefficient; iso-thermal coefficient; inverse method; neutron flux; pule mode; poison evolution; heat transfer; DNBR estimation; Monte-Carlo code; steady state analysis
300 p. · 15x22.8 cm · Paperback
Description
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2. Control Rod Calibration: Reactor Period Method
3. Control Rod Calibration: Approximated Method
4. Estimation of Feedback Temperature Coefficients
5. Sub-Channel Heat Transfer Analysis
6. Operation in Pulse Mode
7. Poison Evolution and Zero-Dimensional Modelling
8. Multi-Physics Modelling and Analyses using Nodal Methods
9. Monte Carlo Modelling and Study using OpenMC
Stefano Lorenzi is a senior researcher and assistant professor in Nuclear Engineering at Politecnico di Milano. He is lecturer of “Experimental Nuclear Reactor Kinetics and “Integration of Nuclear and Renewable Energy for Carbon Neutral Scenarios courses. His research expertise includes control-oriented simulation of Nuclear Power Plants (NPPs), control scheme investigation for NPPs, multiphysics and reduced order modelling, nuclear hybrid systems and integration with cogenerative applications. He participated and is participating in different European research projects on Lead-cooled Fast Reactors (LEADER and PASCAL Projects), Molten Salt Reactors (SAMOFAR and SAMOSAFER projects), Small Modular Reactors (ELSMOR and TANDEM projects) analysis and development. He is the author of more than 70 international papers.
- Includes coverage of the computational models for the prediction of nuclear reactor neutronics and thermal-hydraulics
- Presents a description of experimental setup and procedure using TRIGA reactor and detailed analysis of obtained results and validation of computational predictions
- Contains exercises and applications throughout to deepen knowledge and understanding