An Introduction to the Engineering of Fast Nuclear Reactors 1st Edition by Anthony M. Judd | (PDF) Free Download

Description

An invaluable resource for both graduate-level engineering students and practising nuclear engineers who want to expand their knowledge of fast nuclear reactors, the reactors of the future. This book is a concise yet comprehensive introduction to all aspects of fast reactor engineering. It covers topics including neutron physics; neutron flux spectra; flux distribution; Doppler and coolant temperature coefficients; the performance of ceramic and metal fuels under irradiation, structural changes, and fission-product migration; the effects of irradiation and corrosion on structural materials, irradiation swelling; heat transfer in the reactor core and its effect on core design; coolants including sodium and lead-bismuth alloy; coolant circuits; pumps; heat exchangers and steam generators; and plant control. The book includes new discussions on lead-alloy and gas coolants, metal fuel, the use of reactors to consume radioactive waste, and accelerator-driven subcritical systems.

User’s Reviews

Reviews from Amazon users which were colected at the time this book was published on the website:

⭐I have only looked thru the table of contents but I would recommend “Plentiful Energy: The Story of the Integral Fast Reactor” by Charles E. Till for an exposition of fast neutron technology. The book by Judd ignores all the advances associated with the ALMR, IFR, SPRISM programs probably because Judd’s book was written in 1981.The results are in. Sodium is the coolant, the pool configuration beats the loop design, metal fuel beats oxide fuel, pyroprocess recycling beats the aqueous PUREX process, and super critical CO2 Brayton cycle beats steam Rankine. An SFR with electro magnetic pumps has no moving parts and no corrosion.This SFR design can be made inherently safe, ie. walk away safe. Safety is not dependent upon active systems. The reactor still has control rods to shut down the reactor. In addition, there are gas expansion modules that expand and shut down the reactor with a loss of coolant flow. There is a safety rod held by a magnet that fails as the temperature increases. If all these safety systems fail, the core has a negative reactivity coefficient for temperature increases so that the reactor shuts down as the temperature increases. Unprotected transient overpower, loss of coolant flow, and loss of heat sink do not damage the reactor. The large pool of sodium with a very high coefficient of thermal conductivity acts as a buffer providing time for the reactivity changes to shut down the reactor before any damage is done. The reactor also has a passive decay heat removal system.The primary coolant flow is entirely within the pool reactor vessel. The reactor vessel walls are only 2 in steel as the reactor operates at ambient pressure. Although no pipes go thru the sides of the reactor vessel, making leaks very unlikely, there is an additional guard vessel surrounding the reactor vessel. If a leak develops in the reactor vessel, the sodium coolant will be caught in the guard vessel and the core will not be exposed.To start a 1 GWe reactor, 400 tons of uranium ore are enriched to 15% producing 2 cores of 5 ton each and 390 tons of depleted uranium. There is one core in the reactor and 1 core being recycled. Recycling involves removing the fission products without separating the plutonium from the other actinides. One ton of depleted uranium is added and the core can run from 18 months to 3 years. Thus 400 tons of uranium ore is sent to a regional enrichment plant, 2 cores and 390 tons of depleted uranium are sent to the reactor site, and the reactor can run for 390 years. 400 tons of uranium ore runs a LWR for 2 years.The annual fission product waste from the recycling process weighs about 1 ton and returns to background radiation levels in 300-400 years. The annual waste from a LWR is 25 tons and returns to background radiation level in 2000-4000 years.The world has about 400 reactor year experience with SFR including 30 years of successful operation of EBR-II. In 1986 EBR-II demonstrated walk away safety by cutting all power to the reactor operating at full power. The reactor shut down without incident. The GE SPRISM reactor received preliminary approval from the NRC and GE was ready to construct a demonstration plant in 1998. This is not a research project, it is ready for implementation.The major concern with SFR reactors is the sodium water interaction. By substituting CO2 Brayton cycle for a steam Rankine cycle, this concern is greatly reduced. You also get a large decrease in capital cost and several additional points in thermal efficiency.You probably still need Judd’s book if you are going to design a reactor or it is a course requirement; however all the major design decisions are covered in Till’s book that costs about $18.

⭐This book was an amazing reference. It includes a really broad range of all the most important characteristics in the design of fast spectrum reactors. The largest portion of the book focuses on reactor physics and fuel design, but there is also a relatively thorough discussion of core design, plant design, and safety. While most of the book focuses on sodium-cooled fast reactors (which is to be expected, as this is the most mature of the fast reactor concepts currently under development), there is some information and discussion of lead- and gas-cooled fast reactors, which I enjoyed.While this isn’t the be-all, end-all tome of fast reactor engineering, it’s an excellent introduction to the subject, and for the quality of information contained in it, the price isn’t nearly as bad as a lot of other engineering books of similar caliber.

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