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Design of the Reactor Core for Nuclear Power Plants [Mīkstie vāki]

  • Formāts: Paperback / softback, 69 pages, height x width x depth: 236x157x5 mm, weight: 158 g
  • Sērija : IAEA Safety Standards Series
  • Izdošanas datums: 30-Mar-2020
  • Izdevniecība: IAEA
  • ISBN-10: 9201038194
  • ISBN-13: 9789201038197
  • Mīkstie vāki
  • Cena: 49,51 €
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  • Formāts: Paperback / softback, 69 pages, height x width x depth: 236x157x5 mm, weight: 158 g
  • Sērija : IAEA Safety Standards Series
  • Izdošanas datums: 30-Mar-2020
  • Izdevniecība: IAEA
  • ISBN-10: 9201038194
  • ISBN-13: 9789201038197
The reactor core is the central part of a nuclear reactor where nuclear fission occurs. It consists of four basic systems and components: the fuel (including fuel rods and the fuel assembly structure), the coolant, the moderator and the control rods, as well as additional structures such as reactor pressure vessel internals, core support plates, and the lower and upper internal structure in light water reactors. This Safety Guide provides recommendations on meeting the safety requirements established in SSR-2/1 (Rev. 1) applied to the design of the reactor core for nuclear power plants. The publication addresses the safety aspects of the core design and includes neutronic, thermohydraulic, thermomechanical, and structural mechanical aspects. Other aspects considered are those relating to reactor core control, shutdown and monitoring, and core management.
1 Introduction
1(2)
Background (1.1)
1(1)
Objective (1.2)
1(1)
Scope (1.3-1.8)
1(2)
Structure (1.9, 1.10)
3(1)
2 General Safety Considerations In The Design Of The Reactor Core
3(7)
Management system (2.1)
3(1)
Design objectives (2.2-2.8)
4(1)
Design basis for structures, systems and components of the reactor core (2.9-2.20)
5(3)
Design for safe operation (2.21-2.23)
8(1)
Reactor core safety analysis (2.24-2.27)
8(2)
3 Specific Safety Considerations In The Design Of The Reactor Core
10(39)
General (3.1-3.15)
10(3)
Neutronic design (3.16-3.25)
13(2)
Thermohydraulic design (3.26-3.33)
15(3)
Thermomechanical design of fuel rods and fuel assemblies (3.34-3.76)
18(10)
Mechanical design of core structures and components (3.77-3.88)
28(2)
Reactor core control, shutdown and monitoring systems (3.89-3.138)
30(11)
Core management (3.139-3.166)
41(8)
4 Qualification And Testing
49(3)
General (4.1)
49(1)
Design qualification (4.2-1.5)
49(1)
Inspection (4.6)
50(1)
Testing including prototype assemblies and lead use assemblies (4.7-4.10)
50(2)
References 52(1)
Annex I Supplementary Technical Information 53(13)
Annex II Aspects To Be Addressed In The Design Of The Fuel Rod, Fuel Assembly, Reactivity Control Assembly, Neutron Source Assembly And Hydraulic Plug Assembly 66(3)
Contributors To Drafting And Review 69