Seminar on Hydride Stripping of the Zirconium Claddings of Spent Fuel Elements from Nuclear Power Stations

1977 ◽  
Vol 43 (4) ◽  
pp. 966-966
Author(s):  
A. T. Ageenkov
Keyword(s):  
Nuclear Power ◽  
Spent Fuel ◽  
Power Stations ◽  
Fuel Elements

VALIDATION OF A MONTE CARLO MODEL OF THE FORK DETECTOR WITH A CALIBRATED NEUTRON SOURCE

2014 ◽  
Vol 27 ◽  
pp. 1460151
Author(s):  
ALESSANDRO BORELLA ◽  
LIVIU-CRISTIAN MIHAILESCU
Keyword(s):  
Nuclear Power ◽  
Monte Carlo Model ◽  
Measurement Data ◽  
Nuclear Research ◽  
Research Centre ◽  
Spent Fuel ◽  
The Past ◽  
Research Areas ◽  
Fuel Elements ◽  
Comparison Exercise

The investigation of experimental methods for safeguarding spent fuel elements is one of the research areas at the Belgian Nuclear Research Centre SCK•CEN. A version of the so-called Fork Detector has been designed at SCK•CEN and is in use at the Belgian Nuclear Power Plant of Doel for burnup determination purposes. The Fork Detector relies on passive neutron and gamma measurements for the assessment of the burnup and safeguards verification activities. In order to better evaluate and understand the method and in view to extend its capabilities, an effort to model the Fork detector was made with the code MCNPX. A validation of the model was done in the past using spent fuel measurement data. This paper reports about the measurements carried out at the Laboratory for Nuclear Calibrations (LNK) of SCK•CEN with a 252Cf source calibrated according to ISO 8529 standards. The experimental data are presented and compared with simulations. In the simulations, not only was the detector modeled but also the measurement room was taken into account based on the available design information. The results of this comparison exercise are also presented in this paper.

scholarly journals A novel localization approach for underwater welding vehicles in spent fuel pools via attitude heading reference system and altimeters

2019 ◽  
Vol 16 (2) ◽  
pp. 172988141983054
Author(s):  
Yang Luo ◽  
Jianguo Tao ◽  
Hao Sun ◽  
Zhuang Hao ◽  
Hao Li ◽  
...  
Keyword(s):  
Reference System ◽  
Nuclear Power ◽  
Localization Algorithm ◽  
Spent Fuel ◽  
Beam Angle ◽  
General Applicability ◽  
Underwater Welding ◽  
Power Stations ◽  
Underwater Localization ◽  
Localization Approach

In this article, a novel localization approach incorporating attitude and heading reference system and underwater altimeters is presented to accurately localize the underwater welding vehicles in spent fuel pools of the nuclear power stations. Different from the conventional underwater localization technologies, the presented localization approach is a more suitable approach in cases of confined structured water areas. Firstly, a multi-regions division localization algorithm is proposed for calculating the coordinate of the underwater welding vehicle through data from sensors. Also, considering the attitude errors of the underwater welding vehicle, the beam angle of the altimeters, and the boundary effects of cross-regions, an optimized multi-regions division localization algorithm is introduced for general applicability of the multi-regions division localization. Then, computer simulations are employed to evaluate the validity and the performance of multi-regions division localization and optimized multi-regions division localization. Finally, the efficiency of the proposed approach is confirmed via system experiments. The experimental results are consistent with simulation results which further indicate that the presented approach holds great potential in effective underwater vehicles localization for confined structured water scenarios.

Quantity and Management of Spent Fuel From Prototype and Research Reactors in Germany

2013 ◽  
Author(s):  
Sabine Dörr ◽  
Wilhelm Bollingerfehr ◽  
Wolfgang Filbert ◽  
Marion Tholen
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Storage Management ◽  
Ministry Of Education ◽  
Spent Fuel ◽  
Research Reactors ◽  
Identification Number ◽  
Current State ◽  
Fuel Elements

Within the scope of an R&D project (project identification number FKZ 02 S 8679) sponsored by BMBF (Federal Ministry of Education and Research), the current state of storage and management of fuel elements from prototype and research reactors was established, and an approach for their future storage/management was developed. The spent fuels from prototype and research reactors in Germany that require disposal were specified and were described in regard to their repository-relevant characteristics. As there are currently no casks licensed for disposal in Germany, descriptions of casks that were considered to be suitable were provided. Based on the information provided on the spent fuel from prototype and research reactors and the potential casks, a technical disposal concept was developed. In this context, concepts to integrate the spent fuel from prototype and research reactors into existing disposal concepts for spent fuel from German nuclear power plants and for waste from reprocessing were developed for salt and clay formations.

The Issue of Underground Depositing of High Radioactive Waste

2016 ◽  
Vol 722 ◽  
pp. 59-65
Author(s):  
Markéta Kočová ◽  
Zdeňka Říhová ◽  
Jan Zatloukal
Keyword(s):  
Radioactive Waste ◽  
Nuclear Power ◽  
Power Plants ◽  
High Level Waste ◽  
Spent Fuel ◽  
High Level Radioactive Waste ◽  
Medium Level ◽  
Long Time ◽  
High Level ◽  
Fuel Elements

Nowadays manipulation and depositing of high-level radioactive waste has become the most important issue, which needs to be solved. High-level radioactive waste consists mainly of spent fuel elements from nuclear power plants, which cannot be deposited for long time in surface repositories in the same way as it is possible in case of low and medium level radioactive waste. The most effective and safe solution in longer time horizon seems to be deep geological repository of high level waste. In this process of deposition, large amount of specific conditions needs to be taken into account while designing the whole underground complex, because the materials and structures must fulfil all necessary requirements. Then adequate safety will be ensured.

scholarly journals Material Matters

MRS Bulletin ◽  
1998 ◽  
Vol 23 (3) ◽  
pp. 6-16 ◽  
Author(s):  
W. Stoll
Keyword(s):  
Soviet Union ◽  
Former Soviet Union ◽  
Nuclear Power ◽  
The United States ◽  
Weapons Of Mass Destruction ◽  
Spent Fuel ◽  
Power Stations ◽  
The Soviet Union ◽  
Water Reactors ◽  
Enriched Uranium

The following article is based on a talk for Symposium X presented by Wolfgang Stoll, Chief Scientific Advisor and Consultant in Siemens, Germany, at the 1996 MRS Fall Meeting.Since 1941 when Glenn Seaborg first isolated plutonium in milligram quantities, the total amount converted through neutron capture in U-238 has increased worldwide to about 1,200 tons and continues to grow about 70 tons/year. What was fissioned in situ in operating nuclear power stations is roughly equivalent to 5 billion tons of black coal, while the fission energy contained in those 1,200 tons unloaded in spent fuel is equivalent to another 2 billion tons of coal. About 260 of these 1,200 tons are ready to release their energy in about 4 kg-portions each in microseconds which is equivalent to 10,000 tons of coal. Most people believe this release of energy poses a major threat of the worldwide arsenal of weapons of mass destruction (WMD). The about 20-fold overkill stored in worldwide WMD is considered superfluous after the crumbling of the Soviet Union. Options are sought to dispose of this surplus in a safe, speedy, and controllable manner. While for highly enriched uranium (HEU) (the other nuclear weapons material) dilution into low-enriched uranium and utilization in current light water reactors (LWR) poses market adaptation problems only, and while the worldwide consensus on the elimination of chemical and biological WMD is still in an initial phase, the decision of both the United States (US) and the former Soviet Union (FSU) to remove most of the plutonium out of weapons looks as if it was a firm political decision.

Analytical remote and laboratory control of the reprocessing of fuel elements from nuclear power stations

1974 ◽  
Vol 37 (5) ◽  
pp. 1155-1162 ◽  
Author(s):  
A. E. Klygin ◽  
A. N. Kononov ◽  
V. G. Pastukhov
Keyword(s):  
Nuclear Power ◽  
Laboratory Control ◽  
Power Stations ◽  
Fuel Elements

Problems in shipment of spent fuel from nuclear power stations

1975 ◽  
Vol 39 (1) ◽  
pp. 615-619
Author(s):  
Yu. I. Arkhipovskii ◽  
V. A. Burlakov ◽  
A. N. Kondrat'ev ◽  
E. D. Lyubimov ◽  
A. P. Markovin
Keyword(s):  
Nuclear Power ◽  
Spent Fuel ◽  
Power Stations
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