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Multi-Physics Modelling (MPM) is an innovative simulation technique that looks very promising for the employment in the field of nuclear engineering as an integrative analysis support in the design development of current and innovative nuclear reactors. This book presents a Multi-Physics Modelling (MPM) approach to the analysis of nuclear reactor core behaviour, developed to study the coupling between neutronics and thermo-hydrodynamics. Reference is made to the Molten Salt Reactor, one of the innovative nuclear systems under development in the framework of the Generation IV International Forum, but the same methodology can be applied to other reactor systems.
- Sales Rank: #2076750 in Books
- Published on: 2011-11-01
- Original language: English
- Number of items: 1
- Dimensions: 9.00" h x 6.00" w x .50" l, .55 pounds
- Binding: Paperback
- 140 pages
Most helpful customer reviews
3 of 3 people found the following review helpful.
Chapter 1 is Molter Salt Reactor Technology and worth the cost of the book
By Hill Country Bob
After the front page is a quotation from Mr. David Le Blanc: `The molten salt reactor technology: "Too good to leave on the shelf".
The book is arranged in four chapters, with chapter one describing the technology, and chapter 2 "Heat Transfer in MSRs" Chapter 3 is "Assessment of MSR Thermo-Hydronamics and Newtronics" and chapter 4 "Multi-Physics Modeling Approach".
Chapter 1 is titled "Molten Salt Reactor Technology" and would make an excellent stand alone book. It covers a brief history going back into the 1940s when it was part of a U S program to develop a nuclear powered airplane. Single fluid and two fluid reactors are addressed. A plant layout for a single fluid Molten Salt Breeder Reactor (MSBR) is shown. A MSRE flow diagram is given. A figure showing a schematic representation of a graphite moderated Molten Salt Reactor (MSR) is provided. The issue of safety is addressed. Four different fuel cycles: Actinide burning, Once-through fuel cycle, denatured thorium- U233 breeder cycle and thorium - U233 breeder cycle are addressed. Salts are addressed including lithium and beryllium fluoride salts, and their characteristics in comparison the lead, sodium, helium and water are addressed. Primary loop structural components are addressed. Advantages and drawbacks of the MSR technology is addressed in a short table (2) Table 7 provides a chart of radiotoxicity due to MSBR actinide wastes compared to other fuel cycles. Different concepts of MSRs are addressed including, thermal-spectrum breeders, fast- spectrum breeders, fast- spectrum incinerators, thermal - spectrum incinerators, sub - critical incinerators and Chlorine - salt MSRs. There are a number of excellent tables and graphics illustrating the chapter.
I consider chapter 1 as very informative regarding the state of MSRs and what they can offer for the future. Anyone interested in MSRs will find chapter 1 interesting and a good read. Chapters 2, 3, and 4 are or interest to the MSR designer.
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