Selective extraction of a radionuclide in the presence of other interfering ions is one of the vital steps in the back-end-of-the-nuclear fuel cycle. The presence of interfering cations (such as Ca 21 ) in the radioactive waste and involvement of multiple separation steps are known to be bottlenecks in the efficient Sr 21 extraction. Here, using free energy corrected density functional theory, we have proposed a two-step Sr 21 extraction methodology in nitrate media in the presence of interfering Ca 21 ion using a multitopic ion-pair receptor, which was earlier reported to be strongly selective for K 1 (Kim et al. J. Am. Chem. Soc. 2012, 134, 1782-1792. To depict the correct free energy trend in the proposed extraction processes, the most probable binding mode of the metal (Sr 21 , Ca 21 , and K 1 ) nitrates in the host are identified. In excellent agreement with the previously reported experiment, Crown/Pyrrole (C/P) binding is noted to be the most preferable mode for KNO 3 , where K 1 and NO 2 3 occupied the Crown (C) and Pyrrole (P) site, respectively. However, the divalent metal ions (Ca 21 and Sr 21 ) are noted to marginally prefer Crown/Crown-Pyrrole (C/ CP) mode, in which metal reside at the C site while two nitrates occupy the P site and also simultaneously bind at the outer sphere of C site to coordinate with the metal via monodentate motif.Based on the free energy of extraction, we predict that the selective separation of chemically alike Ca 21 /Sr 21 pair is indeed achievable using this receptor. We propose that once [Sr(NO 3 ) 2 ] is extracted in organic media, the receptor's high affinity toward K 1 in nitrate media can be used to back strip Sr 21 to the aqueous phase. K E Y W O R D S density functional theory, multitopic ion-pair receptor, selective separation
| I N TR ODU C TI ONSelective separation of fission products like radiostrontium ( 89/90 Sr) in the presence of other interfering divalent ions such as, calcium (Ca) is a challenging and an important task which is central to nuclear waste management program. [1][2][3] The primary aim behind extraction of 90 Sr from the nuclear waste is to reduce the volume of high level liquid waste (HLLW) that can further minimize the undesirable decay heat production in the waste. Similarly, waste generated due to the accidental release of 90 Sr into the atmosphere also requires significant chemical treatment to reduce the radionuclide associated long term hazards and restricts its migration in the environment.Considerable research is devoted to find viable separation techniques for the extraction and recovery of Sr 21 . [2][3][4][5][6] The major difficulty in such separation processes is the presence of interfering cations such as, Ca 21 . In addition to this, strong hydration energy barrier of Sr 21 (-330 kcal mol 21 ) also acts as a bottleneck to extract it into the organic phase and thus signifies the need of a proper extractant with available diluents. Several chemical treatments such as nitrate precipitation and ion exchange methods for Sr 21 recovery ...