Methodological and Practical Bases of Providing Information Support to Activities on Environmental Remediation of the Spent Nuclear Fuel and Radioactive Waste Temporary Storage Facility in Gremikha

Author(s):  
D. B. Stepennov ◽  
A. P. Varnavin ◽  
A. A. Zakharchev ◽  
L. Pillette-Cousin

Remediation of a spent nuclear fuel (SNF) and radioactive waste (RW) temporary storage facility is a multifaceted process that includes a number of stages, such as development of a remediation programme, performance of comprehensive engineering and radiological survey, development of a remediation design, removal of SNF and RW up to the site cleanup. At any stage of the remediation, making of justified decisions is ensured by availability and completeness of associated information. Huge amount of information has to be managed. Therefore an information analysis system (IAS) was developed by the National Research Centre «Kurchatov Institute» within the framework of the project for environmental remediation of the SNF and RW temporary storage facility in Gremikha with financial and technical support provided by France (CEA) and the Russian Federation (Rosatom). The IAS accumulates all information about the project: technical and radiological characteristics of objects/facilities, cartographic information, documentation, data on the project participants, technologies and equipment involved. The IAS architecture includes the following functional subsystems: data management, data analytical processing, project management, geoinformation, 3D modeling, and public information. The IAS allows developers and performers of environmental remediation of the SNF and RW temporary storage facility in Gremikha to fulfill tasks arising at all stages of the work. The IAS operating experience can be transferred for use during surveys and remediation of any radiation hazardous facilities.

2018 ◽  
Vol 38 (2) ◽  
pp. 480-509 ◽  
Author(s):  
K Chizhov ◽  
M K Sneve ◽  
N Shandala ◽  
K Siegien-Iwaniuk ◽  
G M Smith ◽  
...  

2018 ◽  
pp. 31-35
Author(s):  
S. Alyokhina ◽  
О. Dybach ◽  
A. Kostikov ◽  
D. Dimitriieva

The definition of the thermal state of containers with spent nuclear fuel is important part of the ensuring of its safe storage during all period of storage facility operation. The this work all investigations are carried out for the storage containers of spent nuclear fuel of WWER-1000 reactors, which are operated in the Dry Spent Nuclear Fuel Storage Facility in Zaporizhska NPP. The analysis of existing investigations in the world nuclear engineering science concerning to the prediction of maximum temperatures in spent nuclear fuel storage container is carried out. The absence of studies in this field is detected and the necessity of the dependence for the maximum temperature in the storage container and temperature of cooling air on the exit of ventilation duct from variated temperatures of atmospheric air and decay heat formulation is pointed out. With usage of numerical simulation by solving of the conjugate heat transfer problems, the dependence of maximum temperatures in storage container with spent nuclear fuel from atmospheric temperature and decay heat is detected. The verification of used calculation method by comparison of measured air temperature on exit of ventilation channels and calculated temperature of cooling air was carried out. By regression analysis of numerical results of studies the dependence of ventilation air temperature from the temperature of atmospheric air and the decay heat of spent nuclear fuel was formulated. For the obtained dependence the statistical analysis was carried out and confidence interval with 95% of confidence is calculated. The obtained dependences are expediently to use under maximum temperature level estimation at specified operation conditions of spent nuclear fuel storage containers and for the control of correctness of thermal monitoring system work.


2022 ◽  
Author(s):  
Rahul Agarwal ◽  
Rama Mohana Rao Dumpala ◽  
Manoj Kumar Sharma ◽  
Donald M Noronha ◽  
Jayashree S Gamare ◽  
...  

Recovery of Plutonium from aqueous carbonate waste solutions generated during reprocessing of spent nuclear fuel is a key concern for sustainable nuclear energy programmes and remediation of radioactive waste. Reported...


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