The Th fuel cycle is attracting interest again globally because of its advantages over the current Pu fuel cycle, such as breeding fissile 233U from fertile 232Th without using a fast reactor, lower minor actinide production and higher Pu burning. However, there are some concerns, such as the small critical mass of the bred 233U. Using 234U, which is not considered an important isotope, may...
The current direction of energy politics adopted by the Japanese government is the utilization of nuclear energy, therefore, the argument of radioactive waste management is becoming increasingly important. To promise a safe, and less environmental load disposal repository for the high-level radioactive waste (HLW), it is necessary to look ahead of future fuel cycle system which intends to use...
Minimizing the volume of nuclear energy waste becomes more and more vital issue year by year. In many countries, the solution of this problem is a corner stone for taking decision on new nuclear build and for dilemma either to extend the national nuclear energy program or to phase out. Rosatom pays special attention to development of technologies aimed at activity and volume reduction for...
As Indonesia is planning to build an experimental power reactor of pebble bed HTGR type, it is important to determine the content of important fission product nuclides of its spent fuel. Identification the amount and type of the FPs is the first step toward the implementation of safeguards policy, management of the spent fuel and addressing the source term strength in case of an accident. The...
Rare earth (RE) oxides are one of the waste streams generated during pyroprocessing of spent nuclear fuel. To immobilize RE oxides in glass, we explored an international simple glass (ISG), alkali borosilicate glass (ABG) and aluminoborosilicate glass (AG). The loading of RE oxides varied within 15 and 56.5 mass%. To characterize glass durability, we performed the 7-day Product consistency...
Current status of the nuclear fuel cycle in Russia is characterized by significant increase in NPP units under construction based on reactor facilities with VVER-1000/1200/TOI. At the same time rapid expansion of the reactor fleet faces the back-end problems that have to be dealt with. These problems concern reprocessing of SNF and management of products generated as a result of the...
The thermal properties and amount of vitrified waste are major factors that determine the eventual disposal area of high-level radioactive waste deep underground. The effect of high burn-up operation of a light-water reactor with UO2 fuel on the amount and thermal properties of vitrified waste under various nuclear fuel cycle conditions was discussed. In addition, the effect of Cs and Sr...
The paper presents the main Russian concepts and projects in the field of spent nuclear fuel and high level liquid waste reprocessing. A new concept of partition was proposed to minimize waste requiring deep geological disposal. The key problems and tasks of the concept are discussed.
Clean energy is most desirable in the world without any problem; nuclear energy can fill the thirst of energy with lower problems. Waste disposal and radiotoxicity is the most challenge issue in nuclear power generation. It is suggested to transmute spent nuclear fuel and especially minor actinide due to it is high contribution of radiotoxicity. We transmute the Np-237 in the LWR AP1000...
The mathematical model of uranium extract purification process from technetium was made in TPU in the CODE-TP media. In order to maximize the adequacy of the CODE-TP calculations, experimental verification of the simulating algorithms for the technological process of the uranium extract purification from technetium using lab-scale liquid chromatography unit (LCU) at JSC VNIINM was carried out....
