MECHANISMS OF RADIATION DAMAGE AND DEVELOPMENT OF STRUCTURAL MATERIALS FOR OPERATING AND ADVANCED NUCLEAR REACTORS

2021 ◽  
pp. 3-20
Author(s):  
V.N. Voyevodin ◽  
G.D. Tolstolutskaya ◽  
M.A. Tikhonovsky ◽  
A.S. Kuprin ◽  
A.S. Kalchenko
Keyword(s):  
Radiation Damage ◽  
Nuclear Power ◽  
Nuclear Reactor ◽  
Structural Materials ◽  
Radiation Resistant ◽  
Properties Of Materials ◽  
Radiation Material ◽  
New Generation ◽  
High Degree

Safety of nuclear reactor (NR) and economic of nuclear power are determined to high degree by structural materials. Study of reasons of change of physical-mechanical properties of materials and of their dimensional stability under irradiation; determination of operation life of elements of nuclear power energetic assemblies in different conditions, selection and development of prospective materials with high radiation resistance are the main objectives of radiation material science. In the presented paper, mechanisms of radiation damage of structural materials for nuclear power and problems of development of radiation-resistant materials for operating and advanced NR of new generation are examined.

Neutron Radiation Effects on Lubricants and O-Rings for Target and Accelerator Applications

2021 ◽  
Vol 1024 ◽  
pp. 127-133
Author(s):  
Matteo Ferrari ◽  
Aldo Zenoni ◽  
Yong Joong Lee ◽  
Alberto Andrighetto
Keyword(s):  
Gamma Radiation ◽  
Radiation Damage ◽  
Radiation Effects ◽  
Nuclear Reactor ◽  
Neutron Radiation ◽  
Radioactive Isotopes ◽  
Structural Level ◽  
Radiation Resistant ◽  
Under Construction ◽  
Neutron Radiation Effects

Lubricants and O-rings are necessarily used for the construction of many accelerator-driven facilities as spallation sources or facilities for the production of radioactive isotopes. During operation, such component will absorb high doses of mixed neutron and gamma radiation, that can degrade their mechanical and structural properties. Experimental radiation damage tests of these components are mandatory for the construction of the facility. Methodologies for irradiation in nuclear reactor mixed fields and post-irradiation examination of lubricating oils, greases and O-rings were developed and are here presented. Samples were characterized with standard mechanical and physical-chemical tests. Parametric studies on the dose rate effects have been performed on O-rings. A case studies for a specific O-ring application in a gate valve has been developed. Some of the tested samples showed a dramatic change of their properties with dose, while others remain stable. Results were collected on nine commercial greases, on one oil and on four commercial elastomeric O-rings. The most radiation resistant among the selected products are now considered for application in facilities under construction. The main mechanisms of neutron and gamma radiation damage on these polymers were investigated at the mechanical and structural level.

The Development of Radiation-Resistant RF Tags for Use at Nuclear Power Plants

2013 ◽  
Author(s):  
Nobuyuki Teraura ◽  
Kunio Ito ◽  
Naoki Takahashi ◽  
Kouichi Sakurai
Keyword(s):  
Radiation Exposure ◽  
Radiation Damage ◽  
Radio Frequency Identification ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Automatic Data ◽  
Radiation Resistant ◽  
Rf Tags ◽  
Rf Tag

RF tags based on RFID (Radio-frequency Identification) technology have been widely used in various fields including power plant construction and maintenance for the purpose of improving the identification and traceability of the many components in the facility. To date, various types of tags have been developed, including tags that are resistant to chemicals or high-temperature environments, which are used in specialized fields. When considering widespread use of RF tags in nuclear power plants, there is a concern about the effects of radiation on the RF tags, because the data stored in the tag may receive radiation damage, resulting in corruption of data. Here, we describe a newly designed RF tag that achieves resistance to radiation damage by attaching a radiation shield layer and incorporating automatic data-correction software. This radiation-resistant RF tag has been tested under real radiation exposure fields to verify the intended radiation-resistant functions. It is expected that the use of these radiation-resistant RF tags with a data reader and database system will increase the capabilities of RF tags applied to nuclear power plants and it is also expected to lead to reductions in worker radiation exposure doses.

Methodology for Verification of the Heat Transfer Crisis in the Nuclear Fuel Assemblies

2013 ◽  
Author(s):  
Anastasiia Zvorykina ◽  
Georgij Sharayevskiy ◽  
Nataliya Fialko ◽  
Nina Sharayevskaya
Keyword(s):  
Nuclear Power ◽  
Nuclear Reactor ◽  
Emergency Operation ◽  
Complex Problem ◽  
Diagnostic Systems ◽  
Software Support ◽  
Nuclear Power Installations ◽  
Safety Operation ◽  
New Generation ◽  
Power Installations

The present-day stage of nuclear-power engineering development raises sharply a number of complicated questions regarding the guarantee of safety operation of nuclear power-generating units of operating and designed Nuclear Power Plant (NPP). The most important of these unsolved technological problems were considered in [1] on the base of analysis of ways of operation reliability improvement for Nuclear Power Installations (NPI) with WWER and RBMK reactors. In connection with the priorities formulated in [1], in papers [2–6] the main aspects of approaches available for solution of most complex problem are considered: the development of methods of early identification of initial phases of emergency operation regimes in such nuclear power-generating units which are critically important for NPI trouble-free operation. It is necessary to stress, that reliable identification of the anomalies mentioned, especially of thermal-hydraulic nature ones in core region of nuclear reactor, must be provided under conditions when such operating troubles can not yet be detected by the issued supervisory instruments of NPI. Taking into account the requirement to prospective diagnostic provision of NPP equipment, in papers [2–5] are underlined that at present time the development of effective methods of anomalies identification in NPI equipment and development of mathematical software support on base of these methods for computer-aided diagnostic systems on base of AI conceptions in structure of hardware of operator support tools of new generation NPP are considered as the main condition which determine the development of diagnostic means with mentioned functional possibilities.

scholarly journals Determination of the safety rods (SA, SB) for optimized power reactor 1000 using the Core simulator OPR1000

2018 ◽  
Vol 1 (6) ◽  
pp. 177-184
Author(s):  
Son An Nguyen ◽  
Nguyen Trung Tran
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Nuclear Reactor ◽  
Boron Concentration ◽  
Power Reactor ◽  
Experimental Simulation ◽  
The Core ◽  
Operation Process

In order to operate a nuclear power plant, ensuring safety is the most important factor. The function of safety rods are to shut down the reactor in case of emergency. The purpose of this paper to show the result of research and determine the value of safety rods SA, SB. Determination of the Boron concentration corresponding to each group of safety rods of OPR1000 nuclear reactor ensures the safely in the whole operation process. Experimental simulation is carried out in the system simulating core reactor OP1R1000 (CoSi OPR1000). The expermental result corresponds with the theoretic calculated result of Sa and Sb with 1500 pcm, 4000 pcm. The concentrations of Boron appropriately are 134 ppm and 284 ppm, respectively.

scholarly journals Challenges to deployment of twenty-first century nuclear reactor systems

2017 ◽  
Vol 473 (2198) ◽  
pp. 20160815 ◽  
Author(s):  
Sue Ion
Keyword(s):  
Nuclear Power ◽  
Potential Role ◽  
Nuclear Reactor ◽  
First Century ◽  
Science And Engineering ◽  
Fuel Cycles ◽  
Small Modular Reactors ◽  
New Generation ◽  
Historical Issues

The science and engineering of materials have always been fundamental to the success of nuclear power to date. They are also the key to the successful deployment and operation of a new generation of nuclear reactor systems and their associated fuel cycles. This article reflects on some of the historical issues, the challenges still prevalent today and the requirement for significant ongoing materials R&D and discusses the potential role of small modular reactors.

Micro/meso-scale computational study of dislocation-stacking-fault tetrahedron interactions in copper

2009 ◽  
Vol 24 (12) ◽  
pp. 3628-3635 ◽  
Author(s):  
Jaime Marian ◽  
Enrique Martínez ◽  
Hyon-Jee Lee ◽  
Brian D. Wirth
Keyword(s):  
Mechanical Properties ◽  
Nuclear Power ◽  
Scaling Laws ◽  
Computational Study ◽  
Numerical Algorithms ◽  
Structural Materials ◽  
Material Behavior ◽  
Dislocation Dynamics ◽  
Dynamics Simulations ◽  
New Generation

In a carbon-free economy, nuclear power will surely play a fundamental role as a clean and cost-competitive energy source. However, new-generation nuclear concepts involve temperature and irradiation conditions for which no experimental facility exists, making it exceedingly difficult to predict structural materials performance and lifetime. Although the gap with real materials is still large, advances in computing power over the last decade have enabled the development of accurate and efficient numerical algorithms for materials simulations capable of probing the challenging conditions expected in future nuclear environments. One of the most important issues in metallic structural materials is the degradation of their mechanical properties under irradiation. Mechanical properties are intimately related to the glide resistance of dislocations, which can be increased severalfold due to irradiation-produced defects. Here, we present a combined multiscale study of dislocation-irradiation obstacle interactions in a model system (Cu) using atomistic and dislocation dynamics simulations. Scaling laws generalizing material behavior are extracted from our results, which are then compared with experimental measurements of irradiation hardening in Cu, showing good agreement.

scholarly journals Dynamics of Radiation Damage in AlN Ceramics under High-Dose Irradiation, Typical for the Processes of Swelling and Hydrogenation

Crystals ◽  
2020 ◽  
Vol 10 (6) ◽  
pp. 546 ◽  
Author(s):  
Artem L. Kozlovskiy ◽  
Dmitriy. I. Shlimas ◽  
Inesh E. Kenzhina ◽  
Daryn B. Borgekov ◽  
Maxim V. Zdorovets
Keyword(s):  
Radiation Damage ◽  
Nuclear Power ◽  
Accelerated Aging ◽  
Structural Materials ◽  
Strength Properties ◽  
Point Of View ◽  
High Dose ◽  
Dose Irradiation ◽  
Fundamental Point ◽  
Nitride Ceramics

The use of nitride ceramics, in particular AlN, as structural materials for nuclear power is primarily limited by their resistance to swelling and hydrogenation processes due to the accumulation of poorly soluble helium and hydrogen ions in the structure of the surface layer. In this regard, research in this area is of great importance not only from a fundamental point of view, but also practical, since any new data on radiation resistance can make a great contribution to the development of the theory of resistance to radiation influences of structural materials of a new generation. This work is devoted to a systematic study and comparative analysis of the dynamics of radiation damage during high-dose irradiation with protons and helium ions in nitride ceramics, which have great potential for use as structural materials for GenIV reactors. The choice of irradiation doses of 1 × 1017–5 × 1017 ion/cm2 is due to the possibility of modeling the processes of radiation damage characteristic of displacements of 10–50 dpa. During the study, the dependences of the change in the dielectric and conductive characteristics of nitride ceramics depending on the radiation dose, as well as on the type of ions, were established. The kinetics of degradation and accelerated aging was determined depending on the type of exposure. The mechanical and strength properties of ceramics were determined.

Feasibility of Molecular Structure Determination With a High Resolution Electron Microscope

1968 ◽  
Vol 26 ◽  
pp. 338-339
Author(s):  
T. A. Welton
Keyword(s):  
Electron Microscope ◽  
Substrate Surface ◽  
Helical Axis ◽  
Base Plane ◽  
Resolution Electron ◽  
High Resolution Electron Microscope ◽  
High Degree ◽  
Degree Of Order ◽  
Purine Pyrimidine

An ultimate design goal for an improved electron microscope, aimed at biological applications, is the determination of the structure of complex bio-molecules. As a prototype of this class of problems, we propose to examine the possibility of reading DNA sequence by an imaginable instrument design. This problem ideally combines absolute importance and relative simplicity, in as much as the problem of enzyme structure seems to be a much more difficult one.The proposed technique involves the deposition on a thin graphite lamina of intact double helical DNA rods. If the structure can be maintained under vacuum conditions, we can then make use of the high degree of order to greatly reduce the work involved in discriminating between the four possible purine-pyrimidine arrangements in each base plane. The phosphorus atoms of the back bone form in projection (the helical axis being necessarily parallel to the substrate surface) two intertwined sinusoids. If these phosphorus atoms have been located up to a certain point on the molecule, we have available excellent information on the orientation of the base plane at that point, and can then locate in projection the key atoms for discrimination of the four alternatives.

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