Uranium processing during the treatment of sodium-bonded spent nuclear fuel

被引：16

作者：

Westphal, BR ^{[1
]}

Mariani, RD ^{[1
]}

机构：

[1] Argonne Natl Lab, Nucl Technol Dept, Idaho Falls, ID 83403 USA

来源：

JOM-JOURNAL OF THE MINERALS METALS & MATERIALS SOCIETY | 2000年 / 52卷 / 09期

关键词：

Uranium; Fuel Assembly; Demonstration Program; Waste Form; Ceramic Waste;

D O I：

10.1007/s11837-000-0182-1

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Several key technical areas have been developed during a demonstration program at Argonne National Laboratory to advance the electrometallurgical treatment of spent nuclear fuel, including equipment operating conditions, uranium-product purity and recovery, and processing rates. Operating conditions for three integral processing steps were optimized based on minimizing the impurities to the final uranium product while meeting program goals for processing rates. The overall recovery of uranium during the process steps was influenced by process conditions as well as the production; rates set forth for the demonstration program.

引用

页码：21 / 25

页数：5

共 46 条

[31] The behavior of uranium and fission products in the processing of model spent nuclear fuel in iron(III) nitrate solutions in the presence of supercritical tributyl phosphate-containing carbon dioxide
M. D. Samsonov
T. I. Trofimov
Yu. M. Kulyako
S. E. Vinokurov
B. F. Myasoedov
Russian Journal of Physical Chemistry B, 2014, 8 : 1033 - 1037
[32] Ceramic-composite waste forms from the electrometallurgical treatment of spent nuclear fuel
C. Pereira
M. Hash
M. Lewis
M. Richmann
JOM, 1997, 49 : 34 - 40
[33] The behavior of uranium and fission products in the processing of model spent nuclear fuel in iron(III) nitrate solutions in the presence of supercritical tributyl phosphate-containing carbon dioxide
Samsonov, M. D.
Trofimov, T. I.
Kulyako, Yu M.
Vinokurov, S. E.
Myasoedov, B. F.
RUSSIAN JOURNAL OF PHYSICAL CHEMISTRY B, 2014, 8 (08) : 1033 - 1037
[34] Quantification of elements in spent nuclear fuel using intrinsic radioactivity for sample excitation and chemometric data processing
Panchuk, Vitaly
Petrov, Yuriy
Semenov, Valentin
Kirsanov, Dmitry
ANALYTICA CHIMICA ACTA, 2023, 1239
[35] CRYSTALLIZATION REFINING OF TARGET PRODUCTS DURING REPROCESSING OF SPENT NUCLEAR FUEL: MATHEMATICAL MODEL OF A LINEAR CRYSTALLIZER
Veselov, S. N.
Volk, V. I.
Kashcheev, V. A.
Podymova, T. V.
Posenitskii, E. A.
ATOMIC ENERGY, 2016, 119 (05) : 344 - 350
[36] Crystallization Refining of Target Products During Reprocessing of Spent Nuclear Fuel: Mathematical Model of a Linear Crystallizer
S. N. Veselov
V. I. Volk
V. A. Kashcheev
T. V. Podymova
E. A. Posenitskii
Atomic Energy, 2016, 119 : 344 - 350
[37] Numerical analysis and experimental validation of planar electrorefiner for spent nuclear fuel treatment using a tertiary model
Yoo, Bung-Uk
Kim, Seung-Hyun
Park, Sung-Bin
Lee, Sung-Jai
Jang, Jun-Hyuk
Paek, Seung-Woo
Lee, Han-Soo
Lee, Jong-Hyeon
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2016, 53 (12) : 2079 - 2089
[38] Quantum-mechanical study of the electronic properties of UxPuyOz compounds formed during the recovery of spent nuclear fuel
Galashev, Alexander Y.
Vorob'ev, Alexey S.
Zaikov, Yuri P.
JOURNAL OF THE SERBIAN CHEMICAL SOCIETY, 2023, 88 (11) : 1125 - 1134
[39] Behavior of Fission Products in the Course of Dissolution of Simulated Spent Nuclear Fuel in Iron Nitrate Solutions and of Recovery of Uranium and Plutonium from the Resulting Solutions
Kulyako, Yu. M.
Perevalov, S. A.
Trofimov, T. I.
Malikov, D. A.
Samsonov, M. D.
Vinokurov, S. E.
Myasoedov, B. F.
RADIOCHEMISTRY, 2011, 53 (06) : 608 - 611
[40] Computer-assisted design and experimental validation of multielectrode electrorefiner for spent nuclear fuel treatment using a tertiary model
Kim, Seung Hyun
Park, Sung Bin
Lee, Sung Jai
Kim, Jeong Guk
Lee, Han Soo
Lee, Jong Hyeon
NUCLEAR ENGINEERING AND DESIGN, 2013, 257 : 12 - 20

← 1 2 3 4 5 →