[en] The results are presented of tests on a model of an atomic electric power plant (AEPP) cooler during excitation simulating seismic activity. The most highly stressed zones of the construction are indicated. The applicability of the modeling method for evaluating the seismic stability of elements of AESS equipment is discussed

[en] The dynamical charcteristics of the heat exchanger representing a horizontal apparatus with a flexible integrated pressurizer are studied. The design analysis for three different fasteners is performed. The computer calculation is performed by the method of finite elements. It is shown that the combination of calculation studies with equipment simulation with the use of models allows to establish reliably main dynamical equipment characteristics and to find out the effect of rigidity of certain construction elements, fastening conditions and presence of liquid on frequency values of free structure vibrations

No abstract available

[en] Technique for tests using NPP equipment models under dynamic loadings is described. Scale and similitude factors are used during selection of model scales and processing of test results. Application of similitude factors of relative deformations, sizes and transfers widens possibilities for material selection during model fabrication

[en] This paper reports on the main direction of activities regarding improvement of technical and economic characteristics of control rods, results of the rod modernization, and perspectives of further improvement of control rods for the fast reactors BN-350 and BN-600. (author). 7 figs, 1 tab., 1 scheme

[en] Post-irradiation examination was performed for scram rods from BOR-60 and BN-600 reactors with hot pressed pellets of boron carbide enriched with ¹⁰B isotope as a neutron absorber. It is concluded that the service life of the scram rods is limited by a decrease of mechanical properties of structural components. The latter should be manufactured of steels and alloys of higher radiation resistance

[en] The BOR-60 reactor control system is described. Tests were performed for scram rods, automatic regulating rods, shim rods. Boron carbide europium oxide a chromium diboride-tantalum diboride alloy were used as absorbers. Protective tubes of rods and absorbing element cans were manufactured of steels 0Kh18N10T and Kh16N15M3B respectively. Based on the study of microstructure, mechanical properties and dimensional stability of absorbing and structural materials it is concluded about operational capability of rods of various design

[en] The present paper is a summary of all results obtained over 25 years of control rods operation, and involves the following data: (1) design and characteristics of the different types of control rods tested during the BOR-60 reactor operation; and (2) main results of post-irradiation examination. (author). 2 figs, 4 tabs

[en] For the reactors on fast neutrons in system of control and protection are used safety rods (SR), made on base enriched by isotope ¹⁰ B boron carbide in kind of hot pressed pellets. The service time of such rods is limited and after operation in reactor during appointed service life they are replaced by new rods. The fulfilling safety rods are subject to utilization and are stored in storage pools. During 1992-1993 in State Scientific Centre Research Institute of Nuclear Reactors researches of safety rods, fulfilling in reactor BOR-60 (1 rod of design 1057-0) and BN-600 (4 rods of a design 1663) and long time storing in pools of storage, were conducted. It was shown, that in rod SR 1057-0 after 537 effective days of operation in reactor BOR-60 and 18 years of storing in pool of storage was undamaged of absorbing pins, the majority of pellet B₄ C have satisfactory conditions and sizes. Simultaneously essential decrease of the mechanical characteristics of absorbing pins claddings and external cover tube of rod was shown. Absorbing pins of rods design 1663, fulfilling various time in the reactor BN-600, not had of damages. Significant quantity of pellets B₄ C have save integrity. Low extension part of a rod, fulfilling 330 effective days, had appreciable bent because of non-uniformity neutron influence, and the material had low fracture toughness. The absorbing pin cladding have reduced the plastic characteristics, The conclusion was made, that the resource of fast reactors safety rods is limited by decrease of the mechanical characteristics of constructional details at low part of rods. Thus the measures on increase service time of the safety rods should first of all provide use as constructional materials radiation resistant steels and alloys. Improvements in should also be introduced a design of rods, having excluding of regular influence of their low part at operation