加速器驱动洁净能系统中的燃耗行为分析

研究了加速器驱动洁净核能系统（ADS）次临界反应堆内核素的演化。分析结果表明：ADS具有嬗变长寿命核废物的能力。从快堆和热堆的比较可知,ADS的快堆具有输出功率大、长寿命超铀放射性废物的累积水平低、裂变产物对反应堆反应性和能量增益影响小等优点。这些优点在利用U－Pu燃料循环的次临界堆中十分明显。对于利用Th-U燃料循环的次临界堆,热堆和快堆都是可以工作的;而对于U－Pu燃料循环的系统,快堆则是较好的选择。     

Problem of the iodine method of purification of zirconium

A method is proposed for the determination of the equilibrium constantsk and k' for the reactions Zr+2I₂–ZrI₄=0 and 2I–I₂=0, which is based on the measurement of the amount of iodine or zirconium liberated in the decomposition of zirconium tetraiodide on a heated surface in the process of establishing equilibrium. The decomposition of the tetraiodide was carried out at 900–1600C on a tungsten filament. The temperature distribution between filament and vessel walls was neglected.The dependence of the sum of atomic and molecular iodine pressures on zirconium tetraiodide pressure was determined at 1430C, and on temperature for 50 mm Hg. The values of kk'² 35 (mm Hg)³ at 1430C and k0.07 mm Hg at 400C, found from the results, differ substantially from known thermodynamic data, but give good agreement between the authors' formula [1] and experimental results on the iodide process of zirconium purification.     

Possibility of deceasing the dimension of the problem of optimal design of self-shielded reactors

Conclusions We note that the approach considered in this paper is applicable to the most dangerous accident situations and their combinations for any type of reactor. In addition, reactors of a definite type have their own matrix of unit values of the criteria. For different reactors such matrices can differ not only by accident situations (variants) but also some criteria (safety functionals characterizing a definite accident process). Although for deterministic substantiation of self-shielding of one or another design, it is necessary to examine all accident regimes of reactor operation, at the preliminary-search stage in the general design process attention can be confined to the most significant (dangerous) situations. This will make it possible to decrease substantially the dimension of the problem and increase the efficiency of the investigations. Moscow Engineering-Physics Institute. Translated from Atomnaya énergiya, Vol. 82, No. 3, pp. 178–184, March, 1997.     

Calculation of emergency situations occurring during the conversion of the research reactor at the Institute of Nuclear Physics of the Academy of Sciences of the Republic of Uzbekistan

Calculations of emergency situations occurring during the conversion of the VVR-SM reactor at the Institute of Nuclear Physics of the Republic of Uzbekistan are presented. Results are presented for the following situations: motion of a compensating rod (two cases), loss of electric power, and obstruction of a fuel assembly. It is shown that safety is maintained for all the emergency situations which were analyzed and the behavior of all zones which were analyzed is actually identical. The computational results will be used for the conversion of VVR-SM to low-enrichment fuel. __________ Translated from Atomnaya énergiya, Vol. 104, No. 6, pp. 339–343, June, 2008.