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Characterization, Properties and Methods of Spent Nuclear Fuel is a comprehensive reference focused on the backend of the nuclear fuel cycle. It is paramount that researche… Read more
LIMITED OFFER
Immediately download your ebook while waiting for your print delivery. No promo code is needed.
Characterization, Properties and Methods of Spent Nuclear Fuel is a comprehensive reference focused on the backend of the nuclear fuel cycle. It is paramount that researchers and engineers involved with spent fuel have a deep understanding of the specific fuel they are handling for both safety and economic reasons, and this book presents various opportunities to optimize both nuclear facilities and processes. It starts with a summary of the topic before presenting a broad and deep analysis of the methods available, including transport, storage, disposal, reprocessing, and accidents.
Fuel characterization is then presented alongside various methods, measurements, codes and calculations which the reader can follow and apply to their own research or setting. With a focus on decision making and safety, this book will benefit all readers involved in spent nuclear fuel and will equip them with a clear understanding of the safest and most economical approaches which best suit their specific setting.
Researchers and professionals in the nuclear industry, particularly those involved in the management of spent nuclear fuel and the back-end of the nuclear fuel cycle
1. Introduction
2 .The back-end of the nuclear fuel cycle
•Situation and history of the nuclear fuel at time of off-loading in reactor
•Transport
•Intermediate storage
•Wet storage in pools
•Dry storage in casks
•Final disposal
•Reprocessing
•Catastrophic accidents
•Requirements
3. Characterization
•Decay heat
4. Calorimetric measurements
5. Indirect determination methods
6. Calculation by codes
•Burn-up (BU), Initial enrichment (IE), Cooling time (CT).
•Criticality – multiplicity
•Nuclear radiation:
7. The radiation field from spent nuclear fuel
•Gamma radiation
•Neutron radiation
•Cherenkov radiation
•Content of the nuclear fuel - nuclide inventory
•Uncertainty, bias and accuracy
8. Uncertainty analysis for characterization of spent nuclear fuel
9. Conservatisms and margin
•Characterization systems
10. Needs and requirements for different parts of the back-end
11. Detectors
12. Data acquisition
13. Decision making
•International and national guidelines
14. International safeguards verification
•Background and international law
•Identification of the nuclear fuel
•Contents of fuel – amount of fissile material
•Missing pins - completeness of fuel assemblies
•Weight
•Decay heat
•Seals and markings
•Authentication of measurement signals and shared characterization systems
15. Fuel information: data and history
16. Codes
17. Nuclear data
•Overview
•Libraries
•Future needs
18. Fuel integrity
•Damaged and failed nuclear fuel
•Nuclear fuel behaviour and risks related to their history and properties
•Long term safety case
19. Nuclear fuel dissolution
•Acceptance criteria
•International and national guidelines
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