On the effects of fission product noble metal inclusions on the kinetics of radiation induced dissolution of spent nuclear fuel

2008 ◽  
Vol 378 (1) ◽  
pp. 55-59 ◽  
Author(s):  
Martin Trummer ◽  
Sara Nilsson ◽  
Mats Jonsson
2013 ◽  
Vol 92 ◽  
pp. 80-86 ◽  
Author(s):  
Åsa Björkbacka ◽  
Saman Hosseinpour ◽  
Magnus Johnson ◽  
Christofer Leygraf ◽  
Mats Jonsson

2020 ◽  
Vol 4 (1) ◽  
Author(s):  
Richard A. Clark ◽  
Michele A. Conroy ◽  
Timothy G. Lach ◽  
Edgar C. Buck ◽  
Kristi L. Pellegrini ◽  
...  

2020 ◽  
Vol 4 (1) ◽  
Author(s):  
Richard A. Clark ◽  
Michele A. Conroy ◽  
Timothy G. Lach ◽  
Edgar C. Buck ◽  
Kristi L. Pellegrini ◽  
...  

2015 ◽  
Vol 17 (10) ◽  
pp. 1760-1768 ◽  
Author(s):  
E. Curti ◽  
A. Puranen ◽  
D. Grolimund ◽  
D. Jädernas ◽  
D. Sheptyakov ◽  
...  

The long-lived fission product79Se is tightly bound to the UO2lattice in spent nuclear fuel; it will thus be released only very slowly from a geological repository for radioactive waste.


1999 ◽  
Vol 556 ◽  
Author(s):  
Fanrong Chen ◽  
Peter C. Burns ◽  
Rodney C. Ewing

Abstract79Se is a long-lived (1.1×106 years) fission product which is chemically and radiologically toxic. Under Eh-pH conditions typical of oxidative alteration of spent nuclear fuel, selenite or selenate are the dominant aqueous species of selenium. Because of the high solubility of metalselenites and metal-selenates and the low adsorption of selenite and selenate aqueous species under alkaline conditions, selenium may be highly mobile. However, 79Se released from altered fuel may be immobilized by incorporation into secondary uranyl phases as low concentration impurities, and this may significantly reduce the mobility of selenium. Analysis and comparison of the known structures of uranyl phases indicate that (SeO3) may substitute for (SiO3OH) in structures with the uranophane anion-topology (α.-uranophane, sklodowskite, boltwoodite) which are expected to be the dominant alteration phases of UO2 in Si-rich groundwater. The structural similarity of guillemninite, Ba[(UO2)3 (SeO3)2O2](H2O) 3 to phurcalite, [(UO2)3(PO4)2O2](H2O)7, suggests that the substitution (SeO3)↔ (PO4) may occur in phurcalite. The close similarity between the sheets in the structures of rutherfordine and [(UO2)(SeO3)] implies that the substitution (SeO3) ↔ (CO3) can occur in rutherfordine. However, the substitutions: (SeO3) ↔ (SiO3OH) in soddyite and (SeO3) ↔ (PO4) in phosphuranylite may disrupt their structural connectivity and are unlikely to occur.


Author(s):  
Jack Law ◽  
Dean Peterman ◽  
Cathy Riddle ◽  
David Meikrantz ◽  
Terry Todd

The Fission Product Extraction (FPEX) Process is being developed as part of the United States Department of Energy Advanced Fuel Cycle Initiative for the simultaneous separation of cesium (Cs) and strontium (Sr) from spent light water reactor (LWR) fuel. Separation of the Cs and Sr will reduce the short-term heat load in a geological repository, and when combined with the separation of americium (Am) and curium (Cm), could increase the capacity of the geological repository by a factor of approximately 100. The FPEX process is based on two highly specific extractants: 4,4',(5')-Di-(t-butyldicyclo-hexano)-18-crown-6 (DtBuCH18C6) and Calix[4]arene-bis-(tertoctylbenzo-crown-6) (BOBCalixC6). The DtBuCH18C6 extractant is selective for strontium and the BOBCalixC6 extractant is selective for cesium. Results of flowsheet testing of the FPEX process with a simulated feed solution in 3.3-cm centrifugal contactors are detailed. Removal efficiencies, distribution coefficient data, coextraction of metals, and process hydrodynamic performance are discussed along with recommendations for future flowsheet testing with actual spent nuclear fuel.


Sign in / Sign up

Export Citation Format

Share Document