Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards
|Publication Date:||1 December 2016|
|ICS Code (Reactor engineering):||27.120.10|
This master matrix standard describes a series of standard practices, guides, and methods for the prediction of neutron-induced changes in light-water reactor (LWR) pressure vessel (PV) and support structure steels throughout a pressure vessel's service life (Fig. 1). Referenced documents are listed in Section 2. The summary information that is provided in Sections 3 and 4 is essential for establishing proper understanding and communications between the writers and users of this set of matrix standards. It was extracted from the referenced standards (Section 2) and references for use by individual writers and users. More detailed writers' and users' information, justification, and specific requirements for the individual practices, guides, and methods are provided in Sections 3 - 5. General requirements of content and consistency are discussed in Section 6.
This master matrix is intended as a reference and guide to the preparation, revision, and use of standards in the series.
To account for neutron radiation damage in setting pressure-temperature
The techniques, variables and uncertainties related to (1) neutron and gamma dosimetry, (2) physics (neutronics and gamma effects), and (3) metallurgical damage correlation procedures and data are addressed in separate standards belonging to this master matrix (1, 17). The main variables of concern to (1), (2), and (3) are as follows:
Steel chemical composition and microstructure,
Steel irradiation temperature,
Power plant configurations and dimensions, from the core periphery to surveillance positions and into the vessel and cavity walls.
Core power distribution,
Reactor operating history,
Reactor physics computations,
Selection of neutron exposure units,
Neutron special effects, and
Neutron dose rate effects.
A number of methods and standards exist for ensuring the adequacy of fracture control of reactor pressure vessel belt lines under normal and accident loads ((1, 7, 8, 11, 12, 14, 16, 17, 23-27), Referenced Documents: ASTM Standards (2.1), Nuclear Regulatory Documents (2.3) and ASME Standards (2.4)). As older LWR pressure vessels become more highly irradiated, the predictive capability for changes in toughness must improve. Since during a vessel's service life an increasing amount of information will be available from test reactor and power reactor surveillance programs, procedures to evaluate and use this information must be used (1, 2, 4-9, 11, 12, 23-26, 28). This master matrix defines the current (1) scope, (2) areas of application, and (3) general grouping for the series of ASTM standards, as shown in Fig. 1.
The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.
2 The boldface numbers in parentheses refer to a list of references at the end of this standard