About: Research of nuclear systems safety and radiation protection for the needs of state supervision

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An Entity of Type : http://linked.opendata.cz/resource/domain/vavai/Aktivita, within Data Space : linked.opendata.cz associated with source document(s)

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rdf:type	http://linked.opendata.cz/resource/domain/vavai/Aktivita
Title	Research of nuclear systems safety and radiation protection for the needs of state supervision (en) Výzkum bezpečnosti jaderných zařízení a radiační ochrany pro potřeby dozorného orgánu (cs)
skos:notation	JB
http://linked.open...ai/cea/pgm/XD_PGM	326
http://linked.open...a/pgm/cilAktivity	Realizace záměrů koncepce v oblasti jaderné bezpečnosti a jaderných materiálů a ochrany před ionizujíícm zářením má za úkol získat pro výkon státního dozoru co nejobjektivnější nástroje a podklady pro hodnocení úrovně zajištění jaderné bezpečnosti a ochrany před ionizujícím zářením (cs) The aim of the implemantation of intentions of the conception in the sphere of nuclear safety and nuclear materials and protection against the ionising radiation is to acquire the tools, as objective as possible, for the performance of state supervision and the supporting materials for the evaluation of the level of assurance of nuclear safety and protection and protection against ionising radiation (en)
http://linked.open...a/pgm/rokUkonceni	2006
http://linked.open...a/pgm/rokZahajeni	1995
http://linked.open...a/pgm/typAktivity	P - Program
http://linked.open...ai/cea/pgm/resort	State Office for Nuclear Safety
is http://linked.open...avai/cep/aktivita of	Special analytical methods for safeguards analysis in connection with IAEA project 93+2 Development and implementation of the best estimate methodology for licensing audit accident analyses of pressurized water reactors for regulatory body needs Experimental programme on Disbonding Defects Type Influence Assessment of RPV integrity Application of a3D fluid-elestic code to analysis of function of VVER 440/213 reactor contaiment with bubble condenser and spray system as pressure suppression system Safety aspects of NPP operation under the conditions of Load-Following Up-grading of cytogenetic methods for the assessment of exposure of humans to higher doses of ionising radiation The elaboration of methods for in situ measurements to characterize the objects contaminated by radionuclides Research of transport of radioactivity in primary circuit of VVER 440 and VVER 1000 with regard to assertion of ALARA principle Spolupráce mezi dozornými orgány evropské unie a zemí %22žadatelů o členství%22 ve střední a východní Evropě Assesment, technical aspects and technology of burnup credit implementation into criticality analyses of spent fuel management systems A development of methods and tools needed for the ISI qualification of cricical areas of VVER 1000 type reactor pressure vessel UT Qualification of in-service inspections for dissimilar weld joints The behaviour of the WWER 440 spend fuel under the condition of long therm dry storage. Assessment of real progress of radiation damage through the VVER reactor pressure vessel wall Methodology of human factor assessment in operation of nuclear installations The analysis of topical problems in radiation protection concerning exposure of the Czech population to ionising radiation Sampling of reactor pressure vessel inner wall cladding for the neutron fluence as-sessment Investigation of radon transport from the foundation soils to the indoor environment through the contact between the building and the subfloor layers Development of methods and tools for analyses of safety important processes of severe accident A development of the method for determination of crack arrest temperature of reactor pressure vessel steels of VVER reactors Research related to best estimate method and uncertainty analysis Probabilistic assessment of reactor pressure vessel fast failure Integrity of Reactor Presure vessels in Accident Conditions Retrospective dosimetry for nuclear energetics Development of the transition temperature curves of VVER reactor pressure vessels materials The elaboration of the method for assessment of VVER 1000 type spent nuclear fuel during long-term dry storage (over 50 years) Development of Nuclear Power Plants Source Terms for Needs of Crisis Staff of the State Office for Nuclear Safety The improvement of the failure data acquisition system for nuclear research reactors Durability and ageing of concrete construction Development of thermohydraulic model of nuclear power plant Temelin and its validation based on plant start-up tests data, development of plant database and plant model notebook for regulatory body (SÚJB´) needs Development and implementation of advanced systems for modelling of radionuclides dispersion in the environment The analysis of criteria for the determination of the reference levels in the case of medical exposure to ionizing radiation during the special diagnostical procedures. The supplementation of the analytical database of chemical compounds Detailed prognostic radon mapping Design of default and accredited identification methods (direct and indirect) of highstake biological agens and toxins Introducing risk-based methods and probabilistic safety assessment (PSA) in the execution of Regulatory body practice Thermohydraulic model of the Nuclear Power Plant Unit development for the independent accident analysis corried out by RELAP5 code Research of Seismic Activity in the NPP Temelín Region Development of Thermohydraulic Model of Nuclear Power Plant with WWER 440 Reactor for Licensing Audit Calculations Development and evaluation of new radon protective measures - applicability of subslab depressurization systems beneath existing houses Radon well ventilation from bedrock Investigation of geophysical methods for the radon risk classification of foundation soils including the development of nex reference sites for comparison measurements Development and testing of a system for removal of radon from water for small water sources Protection against nuclear, biological and chemical agens Research and development of options reducing risks and consequences of severe accidents for Czech NPPs on the basis of advanced experimental and analytical methods Assessment of patient doses in diagnostic radiology Development of software equipment for assessment of radiological impact of nuclear facilities after its serious accidents
is http://linked.open...avai/ves/aktivita of	SSUJ200412004 SSUJ200422004 SSUJ200542004 SSUJ200552004 SSUJ200572004

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