ASME BPVC-III 1968 – 1968 ASME Boiler and Pressure Vessel Code (BPVC) Section III: Rules for Construction of Nuclear Vessels
This includes all supplemental files.
The rules of this section of the Code constitute requirements for the materials design fabrication inspection and testing and certification of vessels for use in the nuclear energy system of any power plant: A nuclear energy system is that part of a power plant that serves the purpose of producing and controlling an output of thermal energy from nuclear fuel.
Vessels for which rules are specified by this Section of the Code are those which are designed
to provide a pressure retaining barrier in a nuclear energy system or for the overall containment of the system. Included are vessels which are designed to contain the reactor coolant or moderator or separate the reactor coolant or moderator from any heat transfer media required in the performance of system functions. Vessels for the collection and dis pos al of nuclear waste from the system are included if they are subject to pressures greater than would prevail if they were vented to atmosphere.
Product Details
- Published:
- 07/01/1968
- Number of Pages:
- 252
- Note:
- This product is unavailable in Ukraine Russia Belarus