The book covers basic approaches to the nuclear fuel state of energy reactors in the last stages of the nuclear fuel cycle, these have been developed by the authors based on Ukrainian Nuclear Power Plant (NPP) operational experience. The book starts by looking at the physical safety basis of water-water energetic reactor (WWER) nuclear fuel. It goes on to discuss modern approaches to the heat exchange modelling in nuclear power plant equipment. Next, the safety criteria when making a decision about dry storage for WWER-1000 fuel assembly are discussed. Then the effect of reactor capacity cyclic changes on energy accumulation of creep formations in fuel cladding is covered in full, along with a chapter on the analysis of WWER-1000 fuel cladding failure. Finally, the book finishes with a description of thermal safety criteria for dry storage of spent nuclear fuel.
The book is essential reading for anyone concerned with NPP maintenance and safety.

lgrsnf/Thermal and Reliability Criteria for Nuclear Fuel Safety.pdf

Maksym Maksymov; Svitlana Alyokhina; Oleksandr Brunetkin

MAKSYM ALYOKHINA, SVITLANA BRUNETKIN, OLEKSANDR MAKSYMOV

River Publishers series in chemical, environmental, and energy engineering, S.l, 2021

Denmark, Denmark

lg3057483

{"isbns":["8770224013","9788770224017"],"last_page":250,"publisher":"River Publishers"}

Front Cover
Thermal and Reliability Criteria for Nuclear Fuel Safety
Contents
Afterword
Preface
List of Figures
List of Tables
List of Abbreviations
1 Physical Safety Basis of WWER Nuclear Fuel
1.1 Fuel Burn-Up as a Nuclear Safety Criterion
1.2 Influence of the Reactor Operating Mode on the Efficiency of WWER-1000 Fuel Cycles
1.3 Design Constraints and Engineer Suitable Coefficients When Designing and Operating WWER Fuel Loads
1.4 Criteria and Methods of Nuclear Fuel Safety Evaluation Under Operation
References
2 Modern Approaches to the Heat Exchange Modeling in NPP Equipment
2.1 Abstract Models
2.2 Generalization of the Mathematical Model
2.3 Simplified Method of the Numerical Solution of Nonstationary Heat Transfer Problem Through a Flat Wall
2.4 Method of Approximate Analytical Solution of a Nonstationary Heat Transfer Problem Through a Flat Wall
References
3 Safety Criteria for WWER-1000 Fuel Assembly When Making a Decision About Its Dry Storage
3.1 Variable Modes of NPP Operation
3.2 Assessment of Emergency of Fuel Assemblies in Light
Water Reactors (LWR)
3.3 Qualitative Evaluation of WWER-1000 Fuel Assemblies
3.4 Performance Criteria of Fuel Elements
References
4 Effect of Reactor Capacity Cyclic Changes on Energy Accumulation of Irreversible Creep Deformations in Fuel Claddings
4.1 Simulation of Technological Parameters of the NPP with WWER-1000 Under Cyclic Loading
4.2 Analysis of the Effect of Parameter Variations of Control Programs on the State of Fuel Assemblies During the Cyclic Change of the Reactor Capacity
4.3 Uniformity of NPP Energy Release Parameters
4.4 Simulation of Fuel Cladding Failure and Axial Offset in the Cyclic Mode of the NPP Operation
References
5 Analysis of WWER 1000 Fuel Cladding Failure
5.1 Initial Data of the Evaluation Model of the Probability of Fuel Cladding Depressurization
5.2 Simulation of Fuel Cladding Reliability
5.3 Computational Method of Fuel Cladding Failure
5.4 Computational Analyses of Stress-strain State of the Fuel Cladding
References
6 Thermal Safety Criteria for Dry Storage of Spent Nuclear Fuel
6.1 Dry Storage of Spent Nuclear Fuel in Ukraine
6.2 Method of Thermal Safety Analysis of Dry Storage of Spent Nuclear Fuel
6.3
Thermal Condition of Containers for Dry Storage of WWER-1000 Spent Nuclear Fuel
References
Index
About the Authors
Back Cover

2021-07-17