{"id":207179,"date":"2024-10-19T13:20:14","date_gmt":"2024-10-19T13:20:14","guid":{"rendered":"https:\/\/pdfstandards.shop\/product\/uncategorized\/astm-e219\/"},"modified":"2024-10-25T06:01:21","modified_gmt":"2024-10-25T06:01:21","slug":"astm-e219","status":"publish","type":"product","link":"https:\/\/pdfstandards.shop\/product\/publishers\/astm\/astm-e219\/","title":{"rendered":"ASTM-E219"},"content":{"rendered":"
Scope<\/strong><\/p>\n 1.1 This test method covers the determination of U atom percent fission that has occurred in U fuel from analysis of the 137<\/b> Cs to U ratio after irradiation.<\/p>\n 1.2 The test method is applicable to high-density, clad U fuel (metal, alloy, ceramic compound) in which no separation of Cs and U has occurred.<\/p>\n 1.3 The test method is best applied to fuels that have aged several months since irradiation. In such material, the 13-day 136<\/b> Cs activity is reduced to a small amount through decay (3).<\/p>\n 1.4 The test method should be restricted to low-exposure samples in which the activity of 134<\/b> Cs is less than that of 137<\/b> Cs. Cesium-134 is produced by neutron capture on fission product 133<\/b> Cs and grows at a rate proportional to the square of the exposure. This capture process limits the test method to samples exposed to less than 0.6 X 10 nvt. This exposure corresponds to burnups of 12 gigawatt days per metric ton of uranium (GWD\/MTU) in Yankee Core I, and 5 GWD\/ MTU in Dresden Core I. Samples with higher exposures may require the use of a lithium-drifted germanium detector to obtain adequate resolution between 134<\/b> Cs and 137<\/b> Cs. The use of such a detector will extend the range of this test method by a factor of about 2. Mass spectrometric isotope dilution analysis of 137<\/b> Cs with 133<\/b> Cs as the isotopic diluent would also overcome 134<\/b> Cs interference.<\/p>\n 1.5 The test method is best applied to fuels where overheating has not caused center melting or grain growth, since high temperatures cause 137<\/b> Cs to distill from the fuel and deposit on cooler regions, such as the cladding. Therefore, cladding should be leached in the dissolver solution or dissolved with the uranium to maintain the true ratio of fission product 137<\/b> Cs to U. Alternatively, burnup in a maximum flux region of a fuel element can be obtained from analyzing a low-flux region of the element. The burnup measured in this position can be related to the burnup in the peak-flux position by a gamma scan of the element. A gamma scan usually represents the distribution of zirconium-95 and is a reflection of the fission distribution integrated over only the most recent months. This is not always a serious disadvantage, since such studies may be made after short irradiations.<\/p>\n 1.6 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.<\/p>\n Keywords<\/strong><\/p>\n Atom percent fission-uranium\/plutonium fuel; Cesium-137 to U ratio; Nuclear fuels (reactor); Radiochemical analysis; Uranium; Uranium-238 fission by-products; Uranium atom percent fission; atom percent fission-uranium fuel, by radiochemical method, test<\/p>\n ICS Code<\/strong><\/p>\n ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)<\/p>\n DOI:<\/strong> 10.1520\/E0219-80R95<\/p>\n<\/div>\n","protected":false},"excerpt":{"rendered":" E219-80(1995) Test Method for Atom Percent Fission in Uranium Fuel (Radiochemical Method) (Withdrawn 2001)<\/b><\/p>\n\n\n
\n Published By<\/td>\n Publication Date<\/td>\n Number of Pages<\/td>\n<\/tr>\n \n ASTM<\/b><\/a><\/td>\n 1995<\/td>\n 3<\/td>\n<\/tr>\n<\/tbody>\n<\/table>\n","protected":false},"featured_media":207184,"template":"","meta":{"rank_math_lock_modified_date":false,"ep_exclude_from_search":false},"product_cat":[464,2637],"product_tag":[],"class_list":{"0":"post-207179","1":"product","2":"type-product","3":"status-publish","4":"has-post-thumbnail","6":"product_cat-27-120-30","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\/207179","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\/207184"}],"wp:attachment":[{"href":"https:\/\/pdfstandards.shop\/wp-json\/wp\/v2\/media?parent=207179"}],"wp:term":[{"taxonomy":"product_cat","embeddable":true,"href":"https:\/\/pdfstandards.shop\/wp-json\/wp\/v2\/product_cat?post=207179"},{"taxonomy":"product_tag","embeddable":true,"href":"https:\/\/pdfstandards.shop\/wp-json\/wp\/v2\/product_tag?post=207179"}],"curies":[{"name":"wp","href":"https:\/\/api.w.org\/{rel}","templated":true}]}}