GB/T 12789.2-1991
Criteria for nuclear reactor instrumentation--Part 2: Pressurized water reactors (English Version)

Standard No.

GB/T 12789.2-1991

Language

Chinese, Available in English version

Release Date

1991

Published By

General Administration of Quality Supervision, Inspection and Quarantine of the People‘s Republic of China

Latest

GB/T 12789.2-1991

Scope

This standard specifies general principles for PWR instrumentation and its application. There are other standards for the complete requirements of nuclear power plant (pressurized water reactor) accident monitoring instruments. This standard applies to pressurized water reactor (PWR) instrumentation. The pressurized water reactor has the following characteristics: a. The pressurized light water coolant is used as the moderator, and there is no obvious boiling in the reactor pressure vessel. The steam to drive the steam turbine is generated in the steam generator; b. The fuel and the primary coolant are contained in a high-integrity shell (primary circuit coolant pressure boundary), which is usually contained in a high-integrity safety Inside the shell structure; c. The solid ceramic fuel is encapsulated in the metal cladding; d. The geometry of the fuel, moderator, and reflective layer is fixed; e. The core control components are moved by a long-distance drive mechanism to achieve reactive operation Control; f. Auxiliary reactivity control is sometimes achieved using fixed placement of neutron absorbing material and/or slowly changing the concentration of neutron absorbing material dissolved in the moderator.

GB/T 12789.2-1991 history

• 1991 GB/T 12789.2-1991 Criteria for nuclear reactor instrumentation--Part 2: Pressurized water reactors

GB/T 12789.2-1991 -All Parts