{"id":24211,"date":"2024-10-17T00:07:44","date_gmt":"2024-10-17T00:07:44","guid":{"rendered":"https:\/\/pdfstandards.shop\/product\/uncategorized\/astm-e264-2008-2\/"},"modified":"2024-10-24T13:30:00","modified_gmt":"2024-10-24T13:30:00","slug":"astm-e264-2008-2","status":"publish","type":"product","link":"https:\/\/pdfstandards.shop\/product\/publishers\/astm\/astm-e264-2008-2\/","title":{"rendered":"ASTM-E264 2008"},"content":{"rendered":"
\n Significance and Use <\/b><\/p>\n

Refer to Guide E 844 for the selection, irradiation, and quality control of neutron dosimeters.<\/p>\n

Refer to Practice E 261 for a general discussion of the determination of fast-neutron fluence rate with threshold detectors.<\/p>\n

Pure nickel in the form of foil or wire is readily available, and easily handled.<\/p>\n

58 <\/sup> Co has a half-life of 70.86 days and emits a gamma ray with an energy of 0.8107593-MeV.<\/p>\n

Competing activities 65 <\/sup> Ni(2.5172 h) and 57 <\/sup> Ni(35.60 h) are formed by the reactions 64 <\/sup> Ni(n, \u03b3 <\/span> ) 65 <\/sup> Ni, and 58 <\/sup> Ni(n,2n) 57 <\/sup> Ni, respectively.<\/p>\n

A second 9.04 h isomer, 58m <\/sup> Co, is formed that decays to 70.86-day 58 <\/sup> Co. Loss of 58 <\/sup> Co and 58m <\/sup> Co by thermal-neutron burnout will occur in environments , <\/sup> having thermal fluence rates of 3 \u00d7 <\/span> 10 12 <\/sup> cm \u2212 <\/span> 2 <\/sup> \u00b7 <\/span> s \u2212 <\/span> 1 <\/sup> and above. Burnout correction factors, R <\/span> , are plotted as a function of time for several thermal fluxes in Fig. 1. Tabulated values for a continuous irradiation time are provided in Hogg, et al.<\/p>\n

Fig. 2 shows a plot of cross section versus energy for the fast-neutron reaction 58 <\/sup> Ni(n,p) 58 <\/sup> Co. This figure is for illustrative purposes only to indicate the range of response of the 58 <\/sup> Ni(n,p) reaction. Refer to Guide E 1018 for descriptions of recommended tabulated dosimetry cross sections.<\/p>\n

Note <\/span> 1\u2014The data is taken from the Evaluated Nuclear Data File, ENDF\/B-VI, rather than the later ENDF\/B-VII. This is in accordance with E 1018, section 6.1, since the later ENDF\/B-VII data files do not include covariance information. For more details see Section H of reference 8.<\/p>\n

FIG. 2 58 <\/sup> Ni(n,p) 58 <\/sup> Co Cross Section <\/span><\/p>\n

1. Scope <\/b><\/p>\n

1.1 This test method covers procedures for measuring reaction rates by the activation reaction 58 <\/sup> Ni(n,p) 58 <\/sup> Co.<\/p>\n

1.2 This activation reaction is useful for measuring neutrons with energies above approximately 2.1 MeV and for irradiation times up to about 200 days in the absence of high thermal neutron fluence rates (for longer irradiations, see Practice E 261).<\/p>\n

1.3 With suitable techniques fission-neutron fluence rates densities above 10 7 <\/sup> cm \u2212 <\/span> 2 <\/sup> \u00b7 <\/span> s \u2212 <\/span> 1 <\/sup> can be determined.<\/p>\n

1.4 Detailed procedures for other fast-neutron detectors are referenced in Practice E 261.<\/p>\n

1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.<\/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. <\/span><\/p>\n

Note <\/span> \u2014The burnup corrections were computed using effective burn-up cross sections of 1650 b for 58 <\/sup> Co(n, \u03b3 <\/span> ) and 1.4E5 b for 58m <\/sup> Co(n, \u03b3 <\/span> ).<\/p>\n

FIG. 1 R <\/span> Correction Values as a Function of Irradiation Time and Neutron Flux <\/span> <\/span><\/p>\n

2. Referenced Documents <\/b> (purchase separately) <\/i> The documents listed below are referenced within the subject standard but are not provided as part of the standard.<\/span><\/p>\n

ASTM Standards <\/b><\/p>\n

E170<\/span> Terminology Relating to Radiation Measurements and Dosimetry E181<\/span> Test Methods for Detector Calibration and Analysis of Radionuclides E261<\/span> Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques E844<\/span> Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706 (IIC) E944<\/span> Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E 706 (IIA) E1005<\/span> Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706 (IIIA) E1018<\/span> Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E706 (IIB) <\/p>\n

Keywords <\/b><\/p>\n

activation; activation reaction; cross section; dosimetry; fast-neutron monitor; neutron metrology; nickel; pressure vessel surveillance; reaction rate; Fast neutron flux\/fluence; Neutron activation reactions; Nickel; Nickel alloys; Radioactivation–fast neutron flux; Threshold detectors–1 MeV;<\/p>\n

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

ICS Number Code 17.240 (Radiation measurements); 27.120.30 (Fissile materials and nuclear fuel technology)<\/p>\n

DOI: <\/b> 10.1520\/E0264-08\n<\/div>\n","protected":false},"excerpt":{"rendered":"

E264-08 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Nickel (Redline)<\/b><\/p>\n\n\n\n\n
Published By<\/td>\nPublication Date<\/td>\nNumber of Pages<\/td>\n<\/tr>\n
ASTM<\/b><\/a><\/td>\n2008<\/td>\n4<\/td>\n<\/tr>\n<\/tbody>\n<\/table>\n","protected":false},"featured_media":24212,"template":"","meta":{"rank_math_lock_modified_date":false,"ep_exclude_from_search":false},"product_cat":[464,2637],"product_tag":[],"class_list":{"0":"post-24211","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\/24211","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\/24212"}],"wp:attachment":[{"href":"https:\/\/pdfstandards.shop\/wp-json\/wp\/v2\/media?parent=24211"}],"wp:term":[{"taxonomy":"product_cat","embeddable":true,"href":"https:\/\/pdfstandards.shop\/wp-json\/wp\/v2\/product_cat?post=24211"},{"taxonomy":"product_tag","embeddable":true,"href":"https:\/\/pdfstandards.shop\/wp-json\/wp\/v2\/product_tag?post=24211"}],"curies":[{"name":"wp","href":"https:\/\/api.w.org\/{rel}","templated":true}]}}