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Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
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NORMA vydána dne 1.9.2021
Označení normy: ASTM E185-21
Datum vydání normy: 1.9.2021
Kód zboží: NS-1036256
Počet stran: 10
Přibližná hmotnost: 30 g (0.07 liber)
Země: Americká technická norma
Kategorie: Technické normy ASTM
Keywords:
ICS Number Code 27.120.10 (Reactor engineering)
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?Guides E482 and E853 describe a methodology for estimation of neutron exposure obtained for reactor vessel surveillance programs. Regulators or other sources may describe different methods. 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. |
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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 modular 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 (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
X2.
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 X2.
1.5?This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee. |
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2. Referenced Documents | ||||||||||||||||||||||||||||||||||||||||||
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