An Overview of Nuclear vs. Non-Nuclear Design Code Requirements for a Candidate Steam Supply System for Commercial Applications

Jetter, Robert

Idaho National Laboratory

关键词: Superconducting Super Collider Next Generation Nuclear Plant Project;    Steam;    43 Particle Accelerators;    Steam Generators;    Ngnp;   

DOI  :  10.2172/1027941
RP-ID  :  INL/EXT-11-22715
RP-ID  :  DE-AC07-05ID14517
RP-ID  :  1027941

美国|英语

来源: UNT Digital Library

【 摘 要 】

The objective is to identify (mostly for industrial end-users) the difference between a Section III nuclear steam generator (classified as Structures, Systems and Components (SSC)) and a Section VIII steam generator in the same general conditions, but used in a conventional application. Specifically, applicable temperature and pressure ranges and a more quantitative description of how materials change, design margins change and required design rigor changes are of interest. This overview focuses on the steam generator pressure boundary but the downstream piping will also be considered. Within the designations of Section III and Section VIII there are subcategories with their specific regions of applicability. Each of these subcategories has evolved their own unique features with respect to design rules and their implementation. A general overview of the various design codes will be provided in sufficient detail to illustrate the major differences; however, a detailed discussion of the various design requirements and their implementation is beyond the scope of this discussion. References (1) and (2) are sources of more detailed information. Also, example wall sizing calculations will be provided to illustrate the application of the relevant design codes under the candidate design conditions. The candidate steam supply Design Conditions are 600C (1112F) and 24MPa (3,480psi). The Operating Conditions or Service Levels will be somewhat lower and the difference shows up in some of the various design methodologies employed.