[en] The paper features the key layout and design decisions of ATETS-150 reactor plant (RP) intended for co-generation of electric and thermal power. RP safety level enables one to locate the nuclear co-generation plant near large cities

[en] NHR development activities in the ex-USSR were initiated in the 1970s mainly due to a growing deficiency of organic fuels needed for heating large cities in the European part of the country. Construction of two pilot nuclear district heating plants with AST-500 NHRs was started in the early 1980s, and by 1989 the first unit in Gorky NDHP was nearly 90% completed. Current activity in this field is concentrated on upgrading the AST-500 design and on the development on this basis of a whole series of heating-only and co-generation reactor plants of unit power ranging from 30 to 600 MW. A brief description of the AST-500 reference NHR design features is given, as well as of the R and D activities that have been carried out for the design decisions and safety validation. (author). 12 refs, 1 tab

[en] On the basis of the AST-500 reference design decisions and of the experience gained in the RF during the pilot NDHPs development and construction, the advanced NHR AST-500M has been developed recently by OKB Mechanical Engineering, as well as a whole series of heating and co-generation reactor plants of various unit power. All the designs represent enhanced safety reactor plants meeting the contemporary national requirements and international recommendations for nuclear plants of the new generation. The main objectives for the advanced NHR development are considered. New design decisions and engineering improvements are described briefly. (author). 3 refs, 4 figs

No abstract available

[en] The experience of the development and creation of the integral AST-500 reactor for district heating with natural coolant circulation has allowed to implement the same concept for ATETS-150 PWR for small power PWR (80-240 MW(e)) with heat usage for process needs. The distinctive features of advanced reactor system and directions of their development are: primary circuit in common pressure vessel, natural coolant circulation, simplicity, passive safety systems with self-actuated controlling devices, reactor vessel enclosed in second (guard) vessel, favourable conditions for management of the most severe accident. (author)

[en] Design bases of new generation nuclear power units (nuclear power plants - NPP, nuclear co-generation plants - NCP, nuclear distract heating plants - NDHP), using integral type PWPS, developed in OKBM, Nizhny Novgorod and trends of design decisions optimization are considered in this report. The problems of diagnostics, servicing and repair of the integral reactor components in course of operation are discussed. The results of safety analysis, including the problems of several accident localization with postulated core melting and keeping corium in the reactor vessel and guard vessel are presented. Information on experimental substantiation of the suggested plant design decisions is presented. (author)

[en] Safety concept of the advanced reactor plant for nuclear district heating plants AST-500M based on inherent self-protection principles and basic engineering decisions, including use of integral reactor lay-out, all-conditions natural coolant circulation, guard vessel, intermediate circuit and double isolating valves on auxiliary pipelines, forming additional closed isolating system, passive safety systems, which are self-actuated at the emergency change of the plant's parameters are presented. Safety is provided without active systems using and personnel intervention. Reached level of assured safety provides limited consequences of the severest accidents in AST-500M and the possibility to locate them in close vicinity of large cities. (author)

[en] In the report are considered design decisions related to realization of passive system principles in AST-500 (nuclear district heating plant) for nuclear district heating plants being in construction and under design in the USSR. High safety-related requirements predetermined a wide application of passive means for accident prevention, protection and restrictions of accidents consequences. Inherent reactor safety, passive protective and isolating systems and devices are referred to the means of this type. In AST-500 plant an improved safety level was shown to be achieved on account of these means and there are possibilities for further improvement. (author). 14 figs

[en] Poster presentation

[en] Short communication