ASTM E185-98

Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E706 (IF)

STANDARD published on 10.1.1998

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The information about the standard:

Designation standards: ASTM E185-98
Note: WITHDRAWN
Publication date standards: 10.1.1998
SKU: NS-43305
The number of pages: 8
Approximate weight : 24 g (0.05 lbs)
Country: American technical standard
Category: Technical standards ASTM

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Annotation of standard text ASTM E185-98 :

Keywords:

Nuclear reactor vessels-light-water cooled, Nuclear reactor vessels-surveillance, Radiation exposure-nuclear materials/applications, Repair by welding (for steel for nuclear/special applications), Steel screens, Steel/stainless steel-nuclear applications, ICS Number Code 27.120.10 (Reactor engineering)

Additional information

1. Scope

1.1 This practice covers procedures for monitoring the radiation-induced changes in the mechanical properties of ferritic materials in the beltline of light-water cooled nuclear power reactor vessels. This practice includes guidelines for designing a minimum surveillance program, selecting materials, and evaluating test results.

1.2 This practice was developed for all light-water cooled nuclear power reactor vessels for which the predicted maximum neutron fluence ( > 1 MeV) at the end of the design lifetime exceeds 1 X 10 17 n/cm (1 X 10 21 n/m ) at the inside surface of the reactor vessel.

1.3 This practice does not provide procedures for monitoring the radiation induced changes in properties beyond the design life, but the procedure described may provide guidance for developing such a surveillance program.

2. Referenced Documents

A751-21	Standard Test Methods and Practices for Chemical Analysis of Steel Products
A370-23	Standard Test Methods and Definitions for Mechanical Testing of Steel Products
E8/E8M-24	Standard Test Methods for Tension Testing of Metallic Materials
E21-20	Standard Test Methods for Elevated Temperature Tension Tests of Metallic Materials
E23-23a	Standard Test Methods for Notched Bar Impact Testing of Metallic Materials (Includes all amendments and changes 4/13/2023).
E170-23	Standard Terminology Relating to Radiation Measurements and Dosimetry
E208-20e1	Standard Test Method for Conducting Drop-Weight Test to Determine Nil-Ductility Transition Temperature of Ferritic Steels (Includes all amendments and changes 2/9/2023).
E482-22	Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
E636-20	Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels
E844-18	Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance
E853-23	Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results
E900-21	Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
E1214-11(2023)	Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance
E1253-21	Standard Guide for Reconstitution of Charpy-Sized Specimens
E1820-23b	Standard Test Method for Measurement of Fracture Toughness (Includes all amendments and changes 7/14/2023).
E1921-23b	Standard Test Method for Determination of Reference Temperature, T0, for Ferritic Steels in the Transition Range (Includes all amendments and changes 3/6/2024).
E2215-19	Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
E2298-18	Standard Test Method for Instrumented Impact Testing of Metallic Materials
E2956-23	Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
	Subsection NB-2000

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