声明
摘要
Abstract
Table of Contents
Chapter 1．Introduction
1．1 Background and Motivation
1．1．1 Nuclear Reactors in Pakistan
1．1．2 CPR1000 Reactor
1．2 Significance of Research Topic
1．3 Literature review
1．4 Objectives
1．5 Structure of Thesis
Chapter 2．Neutron Transport Theory
2．1 Introduction
2．2 Neutron Transport Equation
2．3 Methods to Solve Neutron Transport Equation
2．3．1 Deterministic methods
2．3．2 Stochastic methods
2．4 Other Reactor Physics Codes
2．5 Summary
CHAPTER 3．Introduction to Monte Carlo Method
3．1 Introduction
3．2 Monte Carlo Method in Reactor Physics
3．3 Characteristics of Monte Carlo Code
3．4 Input File of cosRMC Code
3．4．1 Geometry
3．4．2 Material
3．5 Criticality Source Card
3．6 Tallying in cosRMC
3．7 Summary
Chapter 4．Overview and Modeling of CPR1000
4．1 Introduction
4．2 Overview of the PWR Model
4．4 Radial Geometry
4．4．1 Fuel Rod
4．4．2 Instrumentation Guide Tube
4．4．3 Burnable Poison Rod
4．4．4 Control Rod
4．4．5 Fuel Assembly
4．4．6 Reactor Core
4．5 Axial Geometry
4．5．1 Fuel Assembly
4．6 Summary
Chapter 5．Calculations and Results
5．1 Introduction
5．2 Criticality Calculations
5．2．1 Methodology
5．2．2 Criticality Result
5．3 Neutron Flux Distribution
5．3．1 Normalization Factor(m)
5．3．2 Results
5．4 Core power density calculations
5．4．1 Methodology and Result
5．5 Shiclding Calculations of CPR1000
5．5．1 Methodology
5．5．2 Results
5．6 Summary
Chapter 6．Conclusion and Recommendations
6．1 Conclusion
6．2 Recommendations
References
Publications During Study
Acknowledgements
华北电力大学;
华北电力大学(北京);
