Detail of "14017-39-1"

Reference

Plutonium-uranium separation in the Purex process using mixtures of hydroxylamine nitrate and ferrous sulfamate

Plutonium-uranium separation in the Purex process using mixtures of hydroxylamine nitrate and ferrous sulfamate. McKibben, J. M.; Chostner, D. F.; Orebaugh, E. G. (Savannah River Lab., Du Pont de Nemours (E.I.) and Co., Aiken, SC, USA). Report, DP-1656; Order No. DE84004298, 28 pp. Avail. NTIS From: Energy Res. Abstr. 1984, 9(5), Abstr. No. 7256 (English) 1983. DOCUMENT TYPE: Report CA Section: 71 (Nuclear Technology) Lab. studies, followed by plant operation, established that a mixt. of hydroxylamine nitrate [13465-08-2] and ferrous sulfamate (FS) [14017-39-1] is superior to FS used alone as a reductant for Pu in the Purex 1st cycle. FS usage was reduced by ~70% (from 0.12 to 0.04M) compared to the pre-1978 period. This reduced the vol. of neutralized waste due to FS by 194 L/metric ton of U (MTU) processed. The new flowsheet also gives lower Pu losses to waste and at least comparable fission product decontamination. To achieve satisfactory performance at this low concn. of FS, the acidity in the 1B mixer-settler was reduced by using a split-scrub (a low acid scrub in stage 1 and a higher acid scrub in stage 3) to remove acid from the solvent exiting the 1A centrifugal contactor.

Neutron-activation method for determination of uranium and thorium in materials of the semiconductor industry, especially pure aluminum

Neutron-activation method for determination of uranium and thorium in materials of the semiconductor industry, especially pure aluminum. Kueppers, Gottfried; Erdtmann, Gerhard (Forschungszentrum Juelich G.m.b.H., Germany). Ger. DE 4025273 C1 31 Oct 1991, 3 pp. (Germany). CODEN: GWXXAW. CLASS: ICM: G01N033-20. ICS: G01N023-222. APPLICATION: DE 90-4025273 9 Aug 1990. DOCUMENT TYPE: Patent CA Section: 79 (Inorganic Analytical Chemistry) In materials of the semiconductor industry esp. pure Al, U and Th can be detd. by neutron activation anal. using radionuclides Np-239 and Pa-233. The material sample, activated by neutron irradn., is in a nitric acid soln. and treated after carrier re-insertion with a reducing agent. The Np is fixed from a soln. 7429-90-5 and 14017-39-1 are also in the experiment. using an anion-exchange column during which protactinium is passed, is extd. with trialkyl phosphate or phosphine oxide in an org. solvent, and is detd. in the ext. The Np is then eluted from the column and detd. b-spectrophotometrically in the eluate. The Pa-233 activity is detd. g-spectrophotometrically. Detection limits for U and Th are 0.5 ppt and 10 ppt, resp. .