scholarly journals Radiation Tolerant 3D Laser Scanner for Structural Inspections in Nuclear Reactor Vessels and Fuel Storage Pools

2021 ◽  
Vol 2021 ◽  
pp. 1-7
Author(s):  
Luigi De Dominicis ◽  
Mario Carta ◽  
Massimiliano Ciaffi ◽  
Luca Falconi ◽  
Mario Ferri de Collibus ◽  
...  
Keyword(s):  
Dimensional Analysis ◽  
Nuclear Reactor ◽  
Research Reactor ◽  
Spent Nuclear Fuel ◽  
Crack Opening ◽  
Laser Scanner ◽  
Research Centre ◽  
Fuel Storage ◽  
Radiation Tolerant ◽  
Storage Pools

Accurate and timely assessment of displacements and/or structural damages in nuclear reactor vessels’ components is a key action in routine inspections for planning maintenance and repairs but also in emergency situations for mitigating consequences of nuclear incidents. Nevertheless, all these components are maintained underwater and reside in high-radiation fields thus imposing harsh operative conditions to inspection devices which must cope with effects such as Cerenkov radiation background, Total Ionizing Radiation (TID), and occlusions in the detectors’ field of view. To date, ultrasonic techniques and video cameras are in use for inspection of components’ integrity and with measurements of volumetric and surface crack opening displacements, respectively. The present work reports the realization of a radiation tolerant laser scanner and the results of tests in a nuclear research reactor vessel for acquisition of 3D models of critical components. The device, qualified for underwater operation and for withstanding up to 1 mGy of TID, is based on a 515 nm laser diode and a fast-scanning electro-optic unit. To evaluate performances in a significant but controlled environment, the device has been deployed in the vessel of a research reactor operated by ENEA in the Casaccia Research Centre in Rome (Italy). A 3D model of the fuel rods assembly through a cooling water column of 7 m has been acquired. The system includes proprietary postprocessing software that automatically recognizes components of interest and provides dimensional analysis. Possible application fields of the system stretch to dimensional analysis also in spent nuclear fuel storage pools.

A Method of Performing Shutdown Reactivity Measurements in Spent Nuclear Fuel Storage Pools

1981 ◽  
Vol 52 (3) ◽  
pp. 347-353 ◽  
Author(s):  
Samuel H. Levine ◽  
Mortimer A. Schultz ◽  
Daren Chang
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Fuel Storage ◽  
Storage Pools

Shipment of Spent Nuclear Fuel From the Czech Republic for Reprocessing

2014 ◽  
Author(s):  
Josef Podlaha
Keyword(s):  
Czech Republic ◽  
Nuclear Fuel ◽  
Research Reactor ◽  
Spent Nuclear Fuel ◽  
Research Centre ◽  
Packaging System ◽  
The Czech Republic ◽  
The Us ◽  
Global Threat ◽  
High Level

After more than 50 years of operation of the research reactor operated by ÚJV Řež, a. s. (ÚJV) or the Research Centre Řež, as the case may be, a large amount of spent nuclear fuel (SNF) of Russian origin has accumulated. In 2005, ÚJV joined the Russian Research Reactor Fuel Return (RRRFR) program under the US-Russian Global Threat Reduction Initiative (GTRI) and started the process of SNF shipment from the LVR-15 research reactor back to the Russian Federation (RF) using the ŠKODA VPVR/M transport packaging system (TPS). Two SNF shipments from ÚJV were carried out in 2007 and 2013. After the shipments were completed, only low-enriched nuclear fuel with a maximum enrichment below 20% of 235U remained on the territory of the Czech Republic. ÚJV also participates in shipments of SNF from other countries. The services of ÚJV comprise mainly ŠKODA VPVR/M TPS leasing, technical oversight and expertise during cask handling, SNF loading and cask closing and sealing. Up to now, ÚJV has participated in thirteen shipments of SNF from eight countries; one shipment is currently being prepared. High-level radioactive waste (HLW) will be generated from SNF reprocessing. The vitrified HLW will be returned to the Czech Republic as stated in the Russian-Czech Intergovernmental Agreement on Co-operation in Nuclear Energy. The return of the waste represents very complex and complicated work, technically, legally and contractually.

scholarly journals Summary engineering description of underwater fuel storage facility for foreign research reactor spent nuclear fuel

10.2172/34312 ◽  
1994 ◽  
Author(s):  
H.J. Dahlke ◽  
D.A. Johnson ◽  
J.K. Rawlins ◽  
D.K. Searle ◽  
G.W. Wachs
Keyword(s):  
Nuclear Fuel ◽  
Research Reactor ◽  
Spent Nuclear Fuel ◽  
Storage Facility ◽  
Fuel Storage

Development and Testing of an Advanced Neutron-Absorbing Gadolinium Alloy for Spent Nuclear Fuel Storage

2006 ◽  
Vol 155 (2) ◽  
pp. 133-148 ◽  
Author(s):  
Ronald E. Mizia ◽  
Tedd E. Lister ◽  
Patrick J. Pinhero ◽  
Tammy L. Trowbridge ◽  
William L. Hurt ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Fuel Storage

Overview on Fusion Nuclear Technology Experimental Testing

2016 ◽  
Vol 2 (2) ◽  
Author(s):  
Slavomir Entler ◽  
Jan Kysela
Keyword(s):  
Eutectic Alloy ◽  
Nuclear Reactor ◽  
Experimental Testing ◽  
High Heat ◽  
Neutron Field ◽  
Research Centre ◽  
Nuclear Technology ◽  
High Heat Flux ◽  
Research Activities ◽  
Experimental Facilities

Research Centre Rez in the Czech Republic has carried out a number of research and development activities on the nuclear technology of the fusion reactor International Thermonuclear Experimental Reactor (ITER). These contributions have led to the development of numerous experimental facilities. The initial experimental research related to ITER was focused on the technology of the LiPb eutectic alloy, and a production unit and technological channel were constructed. At a later time, material tests were performed in the neutron field of the LVR-15 research nuclear reactor. Interactions of EUROFER 97 and the LiPb eutectic alloy were examined in in-pile and out-pile tests, and the technology of the LiPb was developed. First wall mock-ups were in-pile and out-pile tested under high heat flux (HHF) cycle loads. At present, a full-size mock-up of the ITER Test Blanket System (TBS) and an HHF testing complex are constructed. This paper provides an overview of the research activities and experimental facilities.

scholarly journals Study of corrosion of aluminum alloys of nuclear purity in ordinary water: Part two

2005 ◽  
Vol 20 (2) ◽  
pp. 45-60 ◽  
Author(s):  
Milan Pesic ◽  
Tatjana Maksin ◽  
Gabrijela Jordanov ◽  
Rajko Dobrijevic ◽  
Zoja Idjakovic
Keyword(s):  
Aluminum Alloys ◽  
International Atomic Energy Agency ◽  
Research Reactor ◽  
Atomic Energy ◽  
Spent Fuel ◽  
Research Project ◽  
Energy Agency ◽  
Ordinary Water ◽  
Fuel Storage ◽  
Frame Work

Since 2002, the effects of corrosion on aluminum alloys of nuclear purity in ordinary water of the spent fuel storage pool of the RA re search reactor at VINCA Institute of Nuclear Sciences have been examined in the frame work of the International Atomic Energy Agency Coordinated Research Project "Corrosion of Research Reactor Aluminum Clad Spent Fuel in Water". Coupons were ex posed to the pool water for a period of six months to six years. The second part of this study comprises extensive results obtained by detailed visual and microscopic examinations of the surfaces of the coupons and represents an integral part of the first report on the topic, previously presented in this journal.

scholarly journals Prediction of the maximum temperature inside container with spent nuclear fuel

2018 ◽  
pp. 31-35
Author(s):  
S. Alyokhina ◽  
О. Dybach ◽  
A. Kostikov ◽  
D. Dimitriieva
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Maximum Temperature ◽  
Storage Facility ◽  
Storage Container ◽  
Atmospheric Air ◽  
Decay Heat ◽  
Fuel Storage ◽  
Maximum Temperatures ◽  
Cooling Air

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.

State of the Art of Nuclear Reactor Instrument Automation

1974 ◽  
Vol 96 (4) ◽  
pp. 394-398
Author(s):  
M. Taeschner ◽  
R. Gariod
Keyword(s):  
High Performance ◽  
Nuclear Reactor ◽  
Research Reactor ◽  
State Of The Art ◽  
Nuclear Research ◽  
Automation System ◽  
Nuclear Research Reactor ◽  
High Investment

Due to its complexity, nuclear reactor instrument automation is a challenge to engineers. High investment and running costs of a nuclear research reactor imply the use of advanced equipment and concepts for instrument automation when striving for high performance, reliability, and operational convenience under budgetary pressure. The article describes a successfully operating instrument automation system stressing the important underlying concepts trying to avoid too much details on specific hardware which is dependent on the time when one must order things.

Assessement of the JEFF-3.1.1 Neutron Data Library for FOR CSE of LWR Fuel Storage Pools

2011 ◽  
Vol 59 (2(3)) ◽  
pp. 1174-1178
Author(s):  
Edwin Kolbe ◽  
Alexander Vasiliev ◽  
Hakim Ferroukhi
Keyword(s):  
Neutron Data ◽  
Fuel Storage ◽  
Data Library ◽  
Storage Pools
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