Zobrazeno 1 - 10
of 27
pro vyhledávání: '"M. V. Kormilitsyn"'
Autor:
M. V. Kormilitsyn, L. A. Kormilitsyna, S. B. Pustovalov, A. A. Sedov, S. S. Simonov, S. A. Subbotin, P. A. Fomichenko, T. D. Shchepetina
Publikováno v:
Atomic Energy. 132:143-148
Autor:
P. A. Fomichenko, A. A. Sedov, L. A. Kormilitsyna, S. B. Pustovalov, P. N. Alekseev, S. A. Subbotin, M. V. Kormilitsyn
Publikováno v:
Atomic Energy. 130:1-5
An implementation assessment of PSKD-600 type power reactors was made. It was established that the readiness level of all PSKD-600 nuclear fuel cycle technologies is no lower than TRL5, and most correspond to readiness level no lower than TRL7, i.e.,
Autor:
A. A. Lizin, N. Yu. Nezgovorov, A. G. Osipenko, M. V. Kormilitsyn, S. V. Tomilin, V. V. Ignat’ev
Publikováno v:
Atomic Energy. 126:368-371
Using an experimental stand for studying the solubility of fluorides, measurements were performed at 550–700°C with step 50°C and the solubility of plutonium and americium trifluorides in melt with molar composition 73LiF–27BeF2 was calculated.
Autor:
O. V. Kryukov, L. A. Kormilitsyna, Yu. M. Semchenkov, M. V. Kormilitsyn, A. V. Khaperskaya, Yu. S. Fedorov, O. S. Feinberg, Victor Ignatiev
Publikováno v:
Atomic Energy. 125:279-283
It is proposed that a specialized molten-salt reactor facility for burning long-lived actinides be located in direct proximity to a pilot-demonstration center. A full-scale ZhSR-S with thermal power 2400 MW will make it possible to burn all transuran
Autor:
Victor Ignatiev, A. G. Osipenko, S. V. Tomilin, Sergey A. Konakov, Alexander V. Zagnitko, A. V. Merzlyakov, M. V. Kormilitsyn, A. A. Lizin, Alexander A. Khokhryakov
Publikováno v:
Procedia Chemistry. 21:417-424
The presented key results were obtained in the course of experiments carried out within the PYROSMANI (PYROchemical processes Study for Minor ActiNIdes recycling in molten salt chlorides and fluorides) Project supported by Rosatom. The individual and
Publikováno v:
Russian Metallurgy (Metally). 2015:1168-1173
When considering the full flow charts of processing of radioactive wastes (RAW) on a polyfunctional plant of pyrochemical processing of the spent nuclear fuel of NIIAR fast reactors, we corroborate optimum technical solutions for the preparation of R
Autor:
S. V. Tomilin, V. V. Ignat’ev, N. Yu. Nezgovorov, A. G. Osipenko, M. V. Kormilitsyn, A. A. Lizin
Publikováno v:
Radiochemistry. 57:36-42
Joint solubility of PuF3 and CeF3 in melts of the molar composition 78LiF-7ThF4-15UF4 and 72.5LiF-7ThF4-20.5UF4 in the temperature range 550°-800°C was studied. Anhydrous PuF3 and CeF3 spiked with 144Ce, and also anhydrous ThF4 were synthesized. Is
Autor:
Vladimir A. Volkovich, M. V. Kormilitsyn, L. F. Yamshchikov, A. V. Shchetinskii, A. G. Osipenko, A. O. Maisheva, A. S. Dedyukhin, S. P. Raspopin
Publikováno v:
Russian Metallurgy (Metally). 2014:593-598
The activity of lanthanum is determined in a Ga-In eutectic alloy and alloys with indium in the temperature range 573–1073 K using the electromotive force (emf) method.
Autor:
Hyun-Kyu Lee, Tadashi Inoue, Kazuo Minato, J. Uhlíř, Victor Ignatiev, Richard J. Taylor, Emory D. Collins, Jean-Paul Glatz, M. V. Kormilitsyn, G. DeAngelis, Pascal Baron, Yasuji Morita, J.D. Law, A. V. Khaperskaya, S.M. Cornet, I.T. Kim, Yu.V. Fedorov, T. Koyama, G. D. Del Cul, D. Warin
Publikováno v:
Progress in Nuclear Energy. 117:103091
The results of an international review of separation processes for spent nuclear fuel (SNF) recycling in future closed fuel cycles are reported. This study was made by the Expert Group on Fuel Recycling Chemistry (EGFRC) organised by the Nuclear Ener
Autor:
M. V. Kormilitsyn, L. V. Zaharova, O. E. Gnevashov, A. A. Baranov, V. S. Naumov, S. V. Tomilin, A. A. Lizin, A. G. Osipenko, L. I. Ponomarev, R. K. Gazizov
Publikováno v:
Atomic Energy. 115:11-17
The temperature dependence of the PuF3, AmF3, CeF3, and NdF3 solubility in the eutectic 46.5LiF–11.5NaF–42KF was measured in the interval 550–700°C. Anhydrous plutonium, americium, cerium and neodymium trifluorides were synthesized. The method