{"id":141829,"date":"2024-10-19T08:15:10","date_gmt":"2024-10-19T08:15:10","guid":{"rendered":"https:\/\/pdfstandards.shop\/product\/uncategorized\/astm-e2215-4\/"},"modified":"2024-10-25T00:29:16","modified_gmt":"2024-10-25T00:29:16","slug":"astm-e2215-4","status":"publish","type":"product","link":"https:\/\/pdfstandards.shop\/product\/publishers\/astm\/astm-e2215-4\/","title":{"rendered":"ASTM-E2215"},"content":{"rendered":"

ASTM E2215-15<\/h3>\n

Historical Standard: Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels<\/h4>\n
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ASTM E2215<\/h4>\n

Scope<\/strong><\/p>\n

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1.1<\/span> This practice covers the evaluation of test specimens and dosimetry from light water moderated nuclear power reactor pressure vessel surveillance capsules.<\/p>\n<\/p><\/div>\n

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1.2<\/span> Additionally, this practice provides guidance on reassessing withdrawal schedule for design life and operation beyond design life.<\/p>\n<\/p><\/div>\n

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1.3<\/span> This practice is one of a series of standard practices that outline the surveillance program required for nuclear reactor pressure vessels. The surveillance program monitors the irradiation-induced changes in the ferritic steels that comprise the beltline of a light-water moderated nuclear reactor pressure vessel.<\/p>\n<\/p><\/div>\n

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1.4<\/span> This practice along with its companion surveillance program practice, Practice E185<\/span>, is intended for application in monitoring the properties of beltline materials in any light-water moderated nuclear reactor.2<\/span><\/span><\/p>\n<\/p><\/div>\n

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1.5<\/span> Modifications to the standard test program and supplemental tests are described in Guide E636<\/span>.<\/p>\n<\/p><\/div>\n

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1.6<\/span> The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.<\/p>\n<\/p><\/div>\n

Keywords<\/strong><\/p>\n

irradiation; nuclear reactor vessels (light water moderated); radiation exposure; surveillance (of nuclear reactor vessels);<\/p>\n

ICS Code<\/strong><\/p>\n

ICS Number Code 27.120.10 (Reactor engineering)<\/p>\n

DOI:<\/strong> 10.1520\/E2215-15<\/p>\n<\/div>\n","protected":false},"excerpt":{"rendered":"

E2215-15 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels<\/b><\/p>\n\n\n\n\n
Published By<\/td>\nPublication Date<\/td>\nNumber of Pages<\/td>\n<\/tr>\n
ASTM<\/b><\/a><\/td>\n2015<\/td>\n7<\/td>\n<\/tr>\n<\/tbody>\n<\/table>\n","protected":false},"featured_media":141833,"template":"","meta":{"rank_math_lock_modified_date":false,"ep_exclude_from_search":false},"product_cat":[462,2637],"product_tag":[],"class_list":{"0":"post-141829","1":"product","2":"type-product","3":"status-publish","4":"has-post-thumbnail","6":"product_cat-27-120-10","7":"product_cat-astm","9":"first","10":"instock","11":"sold-individually","12":"shipping-taxable","13":"purchasable","14":"product-type-simple"},"_links":{"self":[{"href":"https:\/\/pdfstandards.shop\/wp-json\/wp\/v2\/product\/141829","targetHints":{"allow":["GET"]}}],"collection":[{"href":"https:\/\/pdfstandards.shop\/wp-json\/wp\/v2\/product"}],"about":[{"href":"https:\/\/pdfstandards.shop\/wp-json\/wp\/v2\/types\/product"}],"wp:featuredmedia":[{"embeddable":true,"href":"https:\/\/pdfstandards.shop\/wp-json\/wp\/v2\/media\/141833"}],"wp:attachment":[{"href":"https:\/\/pdfstandards.shop\/wp-json\/wp\/v2\/media?parent=141829"}],"wp:term":[{"taxonomy":"product_cat","embeddable":true,"href":"https:\/\/pdfstandards.shop\/wp-json\/wp\/v2\/product_cat?post=141829"},{"taxonomy":"product_tag","embeddable":true,"href":"https:\/\/pdfstandards.shop\/wp-json\/wp\/v2\/product_tag?post=141829"}],"curies":[{"name":"wp","href":"https:\/\/api.w.org\/{rel}","templated":true}]}}