[en] The paper presents main topics and problems which arise during creating of regulatory requirements for post accident situations at NPP

[en] Historical reference, experimental base of the Institute, basic trends of the Institute activities such as: physical and technical issues of nuclear reactors and safety aspects incorporate; production of radionuclides and radionuclide products; nuclear fuel cycle; technical issues of ecologically safe technologies are described

[en] Relative different energy neutron radiometry in reactors for preventing accidents caused by uncontrolled reactivity variations is described. 6 refs, 15 figs

[en] This paper is focused in how the regulation issued as consequence of TMI-2 accident, has affected to the Spanish plant describing the main improvement that has been implemented in each plant and providing a general overview of the approach adopted and current status for the different generation of nuclear plants. 3 refs

[en] This report is dedicated to ideology of the computer code, the main purpose of which is the prediction of radiation consequence of fission products release into atmosphere. The principles of mode do not depend on type of reactors. Therefore, it is not necessary to speak about physical characteristics and scenarios of supposed accidents. It is important to have knowledge about range of parameters values, which are important for consequences. 1 fig., 1 tab

[en] This paper is intended to introduce the actual design implementation of the post-accident monitoring system and to provide a good opportunity to understand what issue items are at the design implementation stage for Wolsong 2, 3 and 4. 3 refs, 3 tabs

[en] RISI is currently conducting research on representative samples of NPP cables both during long-term aging and accident simulation, since insulated electrical cables are used to provide instrumentation signals, power, or control to virtually all remotely operated power plant equipment. The objectives of this program are to determine the suitability of these cables for extended life (beyond 40-year design basis) and to assess various cable condition monitoring techniques for predicting remaining cable life. The cables are being aged for long times at relatively mild exposure conditions with various condition monitoring techniques being employed during the aging process. Following the aging process, the cables are being exposed to a sequential accident profile consisting of high dose rate irradiation followed by simulated design basis loss-of-coolant accident steam exposure. This paper presents some results of a study of NPP cables electrical characteristics at normal and accidental conditions. 6 figs

[en] Emergency Response Centre (ERC) of Czech Republic is a highly specialized institution belonging to Nuclear Safety State Administration (SONS), which assures its activities both organizationally and technically. Main function of the ERC in the case of nuclear emergency is to fulfil the needs of SONS, Governmental Committee for Nuclear Emergencies in ER (GCNE ER) and the regional organs of State Authorities concerning the emergency planning and preparedness, evaluation of nuclear emergency consequences, including the emergency management and response. In the case of major failure or accident on NPP, the ERC carries out the performance analysis and review of a given NPP. It also monitors the dosimetric situation and transfers the recommendation to GCNE ER, Regional Emergency Management Committees and to NPP

[en] The objectives of the Specialist's Meeting were: To provide an international forum for presentation and discussion on experience with instrumentation and equipment for monitoring and controlling NPP post-accident situations; to share experience on the design and improvements in the subject area; to identify and describe advanced features for safety and post-accident management improvements. In order to facilitate a structure discussion and not to omit important problem areas, papers on the following subjects were considered to be within the scope of the Specialist's Meeting: Analysis of existing post-accident instrumentation (in terms of range, qualification and redundancy) to support post-accident management. Requirements for post accident instrumentation and equipment - operating experience, regulations, standards; experience in upgrading of the existing instrumentation; instrumentation and equipment for emergency management systems (emergency rooms and national centers); post-accident computerized aids to assist operators; post-accident operating procedures; R and D in post-accident instrumentation, future trends. The present volume contains: (1) the papers presented by national delegates; (2) programme of the meeting; (3) description of the RIAR research facilities; and (4) list of participants. Refs, figs and tabs

[en] The requirements to computer-aided system of accidents analysis, based on symptom-oriented approach to initial events are given in this paper. The purpose, composition and realization of regression analysis algorithms of fast process measurements results under the Minor statistics Conditions are described. The description of information compacting methods for its long storing, on the base of adaptive digitization methods is given. The results of simulation on the base of computers elaborated technical means and applied software are described. (author). 4 refs, 3 figs, 3 tabs