Authors:H. Naik, S. Surayanarayana, V. Mulik, P. Prajapati, B. Shivashankar, K. Jagadeesan, S. Thakare, D. Raj, S. Sharma, P. Bhagwat, S. Dhole, S. Ganesan, V. Bhoraskar, and A. Goswami
The 238U(n, γ)239U reaction cross-section at average neutron energy of 3.7 ± 0.3 MeV from the 7Li(p, n)7Be reaction has been determined using activation and off-line γ-ray spectrometric technique. The 238U(n, γ)239U and 238U(n, 2n)237U reaction cross-sections at average neutron energy of 9.85 ± 0.38 MeV from the same 7Li(p, n)7Be reaction have been also determined using the above technique. The experimentally determined 238U(n, γ)239U and 238U(n, 2n)237U reaction cross-sections were compared with the evaluated data of ENDF/B-VII, JENDL-4.0, JEFF-3.1 and CENDL-3.1. The experimental
values were found to be in general agreement with the evaluated value based on ENDF/B-VII, and JENDL-4.0 but not with the
JEFF-3.1 and CENDL-3.1. The present data along with literature data in a wide range of neutron energies were interpreted in
terms of competition between different reaction channels including fission. The 238U(n, γ)239U and 238U(n, 2n)237U reaction cross-sections were also calculated theoretically using the TALYS 1.2 computer code and were also found to be in
agreement experimental data.
Authors:P. Govindan, S. Sukumar, K. Vijayan, G. Santhosh Kumar, S. Ganesh, Pradeep Sharma, K. Dhamodharan, R. Subba Rao, M. Venkataraman, and R. Natarajan
A novel method has been developed for recovery of plutonium and uranium from carbonate wash solutions generated during solvent
wash process involved in the reprocessing of high burn up FBTR fuel. The proposed method involves a selective coprecipitation
of Pu and U by adding ammonium hydroxide to the pre acidified carbonate wash solution. Substantial removal of DBP by successive
steps of coprecipitation, completely eliminates the possibility of undesired solid formation which is mainly due to the presence
of high content of DBP. By adopting this method, an excellent decontamination factor for DBP has been achieved without any
crud/solid formation. Phosphate content in the final oxide product meets the product specifications. Flowsheet condition necessary
for the recovery process for plutonium from the aqueous carbonate solution is formulated and adopted in the CORAL facility.
Authors:M. Krivopustov, A. Pavliouk, A. Kovalenko, I. Mariin, A. Elishev, J. Adam, A. Kovalik, Yu. Batusov, V. Kalinnikov, V. Brudanin, P. Chaloun, V. Tsoupko-Sitnikov, A. Solnyshkin, V. Stegailov, Sh. Gerbish, O. Svoboda, Z. Dubnicka, M. Kala, M. Kloc, A. Krasa, A. Kugler, M. Majerle, V. Wagner, R. Brandt, W. Westmeier, H. Robotham, K. Siemon, M. Bielewicz, S. Kilim, M. Szuta, E. Strugalska-Gola, A. Wojeciechowski, S. Hashemi-Nezhad, M. Manolopoulou, M. Fragopolou, S. Stoulos, M. Zamani-Valasiadou, S. Jokic, K. Katovsky, O. Schastny, I. Zhuk, A. Potapenko, A. Safronova, Zh. Lukashevich, V. Voronko, V. Sotnikov, V. Sidorenko, W. Ensinger, H. Severin, S. Batsev, L. Kostov, Kh. Protokhristov, Ch. Stoyanov, O. Yordanov, P. Zhivkov, A. Kumar, M. Sharma, A. Khilmanovich, B. Marcinkevich, S. Korneev, Ts. Damdinsuren, Ts. Togoo, and H. Kumawat
An extended U/Pb-assembly was irradiated with an extracted beam of 2.52 GeV deuterons from the Nuclotron accelerator of the
Laboratory of High Energies within the JINR in Dubna, Russia. The lay-out of this experiment and first results are reported.
The Pb-target (diameter 8.4 cm, length 45.6 cm) is surrounded by a natU-blanket (206.4 kg) and used for transmutation studies of hermetically sealed radioactive samples of 129I, 237Np, 238Pu and 239Pu. Estimates of transmutation rates were obtained as result of measurements of gamma-activities of the samples. Information
about the spatial and energy distribution of neutrons in the volume of the lead target and the uranium blanket was obtained
with sets of activation threshold detectors (Al, Y and Au) and solid state nuclear track detectors (SSNTD). An electronic
3He neutron detector was tested on-line. A comparison of experimental data with theoretical model calculations using the MCNPX
program was performed yielding satisfactory results.