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ASTM E185-15e1

Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels (Includes all amendments And changes 12/19/2016).

Automaticky preložený názov:

Štandardné praktiky pre Design programy dohľadu nad Light - voda miernila Jadrová elektráreň reaktorových nádob

NORMA vydaná dňa 1.6.2015

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Informácie o norme:

Označenie normy: ASTM E185-15e1
Poznámka: NEPLATNÁ
Dátum vydania normy: 1.6.2015
Kód tovaru: NS-618092
Počet strán: 9
Približná hmotnosť: 27 g (0.06 libier)
Krajina: Americká technická norma
Kategória: Technické normy ASTM

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Kategórie - podobné normy:

Technika jaderných reaktorů

Anotácia textu normy ASTM E185-15e1 :

Keywords:

ICS Number Code 27.120.10 (Reactor engineering)

Doplňujúce informácie

Significance and Use

4.1 Predictions of neutron radiation effects on pressure vessel steels are considered in the design of light-water moderated nuclear power reactors. Changes in system operating parameters often are made throughout the service life of the reactor vessel to account for radiation effects. Due to the variability in the behavior of reactor vessel steels, a surveillance program is warranted to monitor changes in the properties of actual vessel materials caused by long-term exposure to the neutron radiation and temperature environment of the reactor vessel. This practice describes the criteria that should be considered in planning and implementing surveillance test programs and points out precautions that should be taken to ensure that: (4.2 The methodology to be used in estimation of neutron exposure obtained for reactor vessel surveillance programs is defined in Guides E482 and E853.

4.3 The design of a surveillance program for a given reactor vessel must consider the existing body of data on similar materials in addition to the specific materials used for that reactor vessel. The amount of such data and the similarity of exposure conditions and material characteristics will determine their applicability for predicting radiation effects.

1. Scope

1.1 This practice covers procedures for designing a surveillance program for monitoring the radiation-induced changes in the mechanical properties of ferritic materials in light-water moderated nuclear power reactor vessels. New advanced light-water small molecular reactor designs with a nominal design output of 300 MWe or less have not been specifically considered in this practice. This practice includes the minimum requirements for the design of a surveillance program, selection of vessel material to be included, and the initial schedule for evaluation of materials.

1.2 This practice was developed for all light-water moderated nuclear power reactor vessels for which the predicted maximum fast neutron fluence (E > 1 MeV) exceeds 1 × 10²¹ neutrons/m ² (1 × 10¹⁷ n/cm²) at the inside surface of the ferritic steel reactor vessel.

1.3 This practice does not provide specific procedures for monitoring the radiation induced changes in properties beyond the design life. Practice E2215 addresses changes to the withdrawal schedule during and beyond the design life.

1.4 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

Note 1: The increased complexity of the requirements for a light-water moderated nuclear power reactor vessel surveillance program has necessitated the separation of the requirements into three related standards. Practice E185 describes the minimum requirements for design of a surveillance program. Practice E2215 describes the procedures for testing and evaluation of surveillance capsules removed from a reactor vessel. Guide E636 provides guidance for conducting additional mechanical tests. A summary of the many major revisions to Practice E185 since its original issuance is contained in Appendix X1.

Note 2: This practice applies only to the planning and design of surveillance programs for reactor vessels designed and built after the effective date of this practice. Previous versions of Practice E185 apply to earlier reactor vessels. See Appendix X1.

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