Precision determination of252Cf half-life and the time dependence of the neutron flux of a Ra - Be(?, n) source

Atomic Energy ◽  
1992 ◽  
Vol 73 (6) ◽  
pp. 1015-1017
Author(s):  
V. T. Shchebolev ◽  
N. N. Moiseev ◽  
Z. A. Ramendik
1961 ◽  
Vol 39 (3) ◽  
pp. 381-384 ◽  
Author(s):  
R. H. Betts ◽  
P. Glentworth

A rare earth activity of half-life 19 ± 1 min, produced by irradiating tantalum in the fast neutron flux of the NRX reactor has been shown to be a lutetium nuclide. The 19 ± 1 min activity was ascribed to Lu178 produced by the Ta181 (n, α)Lu178 reaction. Three γ rays of 450 ± 15 kev, 320 ± 15 kev, and 680 ± 15 kev (very weak) are associated with the 19 ± 1 min Lu178 activity.


2021 ◽  
Vol 253 ◽  
pp. 01005
Author(s):  
Ivan Haysak ◽  
Vasyl Martishichkin ◽  
Yevgen Harapko ◽  
Robert Holomb ◽  
Karel Katovsky

The neutron generation technique was tested on the microtron M-10 with an output electron beam of 8.7 MeV. Given the low energy that the microtron can provide to electrons, the bremsstrahlung induced photonuclear reaction 9Be (γ, n), which has a low threshold, was chosen for neutron generation. Cobalt and indium targets were tested as activation detectors to estimate the neutron flux density. In the cobalt target, the isomeric state of 60mCo with an energy of 58.6 keV and a half-life of 10.5 minutes is well activated. Two well-known additional gamma lines of standard cobalt source permit to clarify the absolute value of the neutron flux. The activated indium target has four gamma lines bound to the 116mIn isomer β- decaying with the half-life of 54.4 minutes, what is convenient for measurement of gamma spectrum. Despite the low energy of the output electron beam, at a beam intensity of 5 μA it is possible to obtain an almost isotropic neutron flux of 107 n/(s∙cm2).


1954 ◽  
Vol 32 (2) ◽  
pp. 94-97 ◽  
Author(s):  
L. G. Cook ◽  
K. D. Shafer

The positron emitting Na22 of 2.6 year half-life has been prepared in a nuclear reactor by the double reaction Li6(n, α)H3, Ne20(H3, n)Na22. The over-all yield was 2.3 × 10−7 atoms of Na22 per atom of tritium formed. Eleven grams of lithium as aluminum alloy turnings in a neon atmosphere at 200 p.s.i. was irradiated for 175 days in a neutron flux of about 4 × 1012 n./cm.2/sec. About 380 μc. of Na22 was obtained in a sodium extract having a specific activity of 10 mc. Na22/gm. of Na23. A specific activity in the curie/gm. level would be expected from a longer irradiation in the highest flux (6 × 1013 n./cm.2/sec.) in the NRX reactor. The separation and purification of the sodium proved practicable by paper chromatography or ion exchange; the analyses for trace Li and Na23 were carried out by radioactivation.


1967 ◽  
Vol 22 (11) ◽  
pp. 1783-1792 ◽  
Author(s):  
T. Kirsten ◽  
W. Gentner ◽  
O. Müller

The stable He-, Ne-, Ar-, Kr- and Xe-isotopes and the Te-, K-, U-, Th- and Se-concentrations in a Precambrian bismuth-tellurium ore have been measured. We have found an age of 0.53 x 109 y with K-Ar, 0.55 x 109 y with U/Th-He4 and 1.56 x 109 y by the U-Xe136 method.The Xe131-excess and part of the Xe129-excess result from n-capture and subsequent decay of Te128and Te130. The remaining part of the Xe129-excess and the high U-Xe136 age give evidence for a higher neutron flux before the last cooling of the ore. The tellurium was probably associated with much more uranium than now. Before 0.54 x 109 y, differentiation of this uranium occured. Moreover, He and Ar but not all of the Xe were removed at this time. After cooling, the Xe129excess was formed by the decay of the long-lived I129 which had been formed from (n,γ) reactions on Te128 by the higher neutron flux.From the excess in Xe130, a half life for the double β-decay of Te130 of 6.2 x 1020 y is calculated.Besides fission-Kr, there is an excess of Kr with atmospheric composition and in addition an excess of Kr82 and Kr83 also. From the Kr82-excess and the selenium content a lower limit for the Se82-double β-decay half life of T1/2≥ 1018 y is calculated. No evidence is given for Ar38 from U-fission.


Metrologia ◽  
2018 ◽  
Vol 55 (4) ◽  
pp. 460-485 ◽  
Author(s):  
A T Yue ◽  
E S Anderson ◽  
M S Dewey ◽  
D M Gilliam ◽  
G L Greene ◽  
...  

1953 ◽  
Vol 31 (6) ◽  
pp. 903-910 ◽  
Author(s):  
F. Brown ◽  
J. L. Wolfson ◽  
L. Yaffe

Activity of approximately 105 min. half-life has been detected in samples of Co59 irradiated at high neutron fluxes in the NRX reactor. By a study of the yield as a function of neutron flux and time of irradiation this activity was demonstrated to be due to Co61 (105 min.) formed by neutron capture in Co60. The pile neutron capture cross sections were found to be 95 ± 45 barns and 6.0 ± 1.4 barns for the Co60* (10.5 min.) and Co60 (5.25 yr.) isomers respectively.


Author(s):  
Abdessamad Didi ◽  
Ahmed Dadouch ◽  
Hassane El Bekkouri

Objective: Currently, nuclear medicine is becoming increasingly important, through the discovery of several medical radioisotopes, which are used in diagnosis, treatment, and medical imaging. Among the most important radionuclide which is commonly used is iodine-131, with a half-life of 8.02 d. Iodine-131 is one of the mainly essential elements in nuclear medicine. Since their first use, several studies have been conducted to meet the world need of hospital specialists in nuclear medicine. The purpose of this study was to participate in a lawsuit about the feasibility of producing 131I.Methods: using neutron activation of the dioxide of tellurium (TeO2) under a neutron flux which varies between 5 1011 and 1013 n/cm²s for 4, 6 and 8 hours** per irradiation cycle during 5 d, and used the Fortron90 Code to calculate the activity of iodine-131.Results: The result of the activity of iodine-131 found about 4,634 Curie with an irradiation of 4 hours** per day and 9.381 Curie with an activation of 8 hours** per day.Conclusion: Production of iodine-131 can be very effective if an acceptable capsule is used for different masses of tellurium and a neutron flux in a nuclear reactor.


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