Vacuum Systems for Dynamic Studies of the Engineering Properties of Materials During Exposure to Nuclear Reactor Irradiation

2009 ◽  
pp. 30-30-21
Author(s):  
O. H. Hill ◽  
E. E. Kerlin ◽  
E. T. Smith
Keyword(s):  
Nuclear Reactor ◽  
Engineering Properties ◽  
Reactor Irradiation ◽  
Dynamic Studies ◽  
Properties Of Materials ◽  
Vacuum Systems

scholarly journals JSI TRIGA neutron and gamma field characterization by TLD measurements

2020 ◽  
Vol 225 ◽  
pp. 04034
Author(s):  
Klemen Ambrožič ◽  
Klaudia Malik ◽  
Barkara Obryk ◽  
Luka Snoj
Keyword(s):  
Radiation Field ◽  
Radiation Effects ◽  
Nuclear Reactor ◽  
Measurement Techniques ◽  
Field Measurements ◽  
Reactor Irradiation ◽  
Fission Chamber ◽  
Start Up ◽  
Gamma Field ◽  
Irradiation Facilities

A well characterized radiation field inside a research nuclear reactor irradiation facilities enables precise qualification of radiation effects to the irradiated samples such as nuclear heating or changes in their electrical or material properties. To support the increased utilization of the JSI TRIGA reactor irradiation facilities in the past few years mainly on account of testing novel detector designs, electronic components and material samples, we are working on increasing the neutron and gamma field characterization accuracy using various modeling and measurement techniques. In this paper we present the dose field measurements using thermo-luminescent detectors (TLD’s) with different sensitivities neutron and gamma sensitivities, along with multiple ionization and fission chamber. Experiment was performed in several steps from reactor start-up, steady operation and a rapid shutdown, during which the ionization and fission chamber signals were acquires continuously, while the TLD’s were being irradiated at different stages during reactor operation and after shutdown, to also capture response to delayed neutron and gamma field. The results presented in this paper serve for validation of JSI designed JSIR2S code for delayed radiation field determination, initial results of its application on the JSI TRIGA TLD measurements will also be presented.

scholarly journals FRICTION COEFFICIENT OF MUNICIPAL SOLID WASTE COMPONENTS

2020 ◽  
Vol 7 (7) ◽  
pp. 1-7
Author(s):  
Yesuenyeagbe A.K. Fiagbe ◽  
Emmanuel W. Ramde
Keyword(s):  
Friction Coefficient ◽  
Municipal Solid Waste ◽  
Solid Waste ◽  
Coefficient Of Friction ◽  
Engineering Properties ◽  
Engineering Systems ◽  
Critical Property ◽  
Properties Of Materials ◽  
Wooden Surface ◽  
Wood Surfaces

Engineering properties of materials includes coefficient of friction (COF) which are basic in design performance of engineering systems. The COF can be considered as very important in design of handling tools. Various types of handling tools and equipment are used at various stages of disposal and treatment of MSW and COF is one critical property. This paper presents estimate of COF of municipal solid waste components. The components of the municipal solid waste are paper, plastic, organic and others. The estimation of the COF was done using an inclino-tribometer. Waste from 16 sample locations were used with 6 surfaces which are considered to be of relevant. It was estimated that Formica surface has the least COF values and range from 0.269 and 0.312 with ‘others’ – formica surface tribosystem being the least. It was also found that paint application on wooden surface with oil paint would increase COF as compared to applying emulsion on same wooden surface. The study pointed out that polishing with vanish is the best way to reduce COF in wood surfaces. It was also observed that painting metal surfaces with oil paint will increase the COF than when the same metal was left unpolished or unpainted.

DESIGN OF A LARGE EXPLOSIVE CONTAINMENT CAPSULE FOR NUCLEAR REACTOR IRRADIATION

1968 ◽  
Vol 152 (1) ◽  
pp. 773-791
Author(s):  
Louis Avrami ◽  
Everett Dalrymple ◽  
Frank Schwartz
Keyword(s):  
Nuclear Reactor ◽  
Reactor Irradiation

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.

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