scholarly journals A Short Critique on Development and Properties of B4C Dispersed Epoxy and Rubber Based Irradiation Shielding Materials

The present article deals with the review on the development and the after effect of irradiation exposure on the properties and characteristics of some B4C polymeric irradiation shielding materials. The smorgasbord of radiations such as alpha, beta, neutron and gamma and their effects not only on biotic but also on a-biotic environments lead to the development of irradiation shielding materials. This article confirms the fabrication of shielding materials that trades off the factor weight without compensating the irradiation shielding ability however possibly by studying material with high thermal neutron absorption and other attenuation factors. One such material is polymers and its allied materials owing to the presence of rich in hydrogen content and the tendency to augment particles within themselves made them suitable for the above mentioned purpose. The details of fabrication and the effects on the mechanical properties are well discussed in this work

Materials ◽  
2021 ◽  
Vol 14 (2) ◽  
pp. 418
Author(s):  
Anna Veverková ◽  
Dalibor Preisler ◽  
Mariia Zimina ◽  
Tereza Košutová ◽  
Petr Harcuba ◽  
...  

Low-alloyed zirconium alloys are widely used in nuclear applications due to their low neutron absorption cross-section. These alloys, however, suffer from limited strength. Well-established guidelines for the development of Ti alloys were applied to design new two-phase ternary Zr alloys with improved mechanical properties. Zr-4Sn-4Nb and Zr-8Sn-4Nb alloys have been manufactured by vacuum arc melting, thermo-mechanically processed by annealing, forging, and aging to various microstructural conditions and thoroughly characterized. Detailed Scanning electron microscopy (SEM) analysis showed that the microstructural response of the alloys is rather similar to alpha + beta Ti alloys. Duplex microstructure containing primary alpha phase particles surrounded by lamellar alpha + beta microstructure can be achieved by thermal processing. Mechanical properties strongly depend on the previous treatment. Ultimate tensile strength exceeding 700 MPa was achieved exceeding the strength of commercial Zr alloys for nuclear applications by more than 50%. Such an improvement in strength more than compensates for the increased neutron absorption cross-section. This study aims to exploit the potential of alpha + beta Zr alloys for nuclear applications.


Author(s):  
S. Fujishiro

The mechanical properties of three titanium alloys (Ti-7Mo-3Al, Ti-7Mo- 3Cu and Ti-7Mo-3Ta) were evaluated as function of: 1) Solutionizing in the beta field and aging, 2) Thermal Mechanical Processing in the beta field and aging, 3) Solutionizing in the alpha + beta field and aging. The samples were isothermally aged in the temperature range 300° to 700*C for 4 to 24 hours, followed by a water quench. Transmission electron microscopy and X-ray method were used to identify the phase formed. All three alloys solutionized at 1050°C (beta field) transformed to martensitic alpha (alpha prime) upon being water quenched. Despite this heavily strained alpha prime, which is characterized by microtwins the tensile strength of the as-quenched alloys is relatively low and the elongation is as high as 30%.


1959 ◽  
Vol 37 (5) ◽  
pp. 531-536 ◽  
Author(s):  
H. R. Fickel ◽  
R. H. Tomlinson

The effective neutron absorption cross section of Xe135 has been measured with a mass spectrometer by observing the variation in the Cs135/Cs137 fission yield ratio obtained at various thermal neutron fluxes. Values of 3.15 ± 0.06 megabarns and 3.27 ± 0.11 megabarns have been determined for neutron temperatures of 120 °C and 137 °C respectively.


1983 ◽  
pp. 143-151
Author(s):  
J.A. CZUBEK ◽  
K. DROZDOWICZ ◽  
E. KRYNICKA-DROZDOWICZ ◽  
A. IGIELSKI ◽  
U. WOźNICKA

Metals ◽  
2019 ◽  
Vol 10 (1) ◽  
pp. 22 ◽  
Author(s):  
Lin Tian ◽  
Dominik Tönnies ◽  
Moritz Hirsbrunner ◽  
Tim Sievert ◽  
Zhiwei Shan ◽  
...  

In this work, structural and mechanical properties of hydrogen-charged metallic glass are studied to evaluate the effect of hydrogen on early plasticity. Hydrogen is introduced into samples of a Zr-based (Vit 105) metallic glass using electrochemical charging. Nanoindentation tests reveal a clear increase in modulus and hardness as well as in the load of the first pop-in with increasing hydrogen content. At the same time, the probability of a pop-in occurring decreases, indicating that hydrogen hinders the onset of plastic instabilities while allowing local homogeneous deformation. The hydrogen-induced stiffening and hardening is rationalized by hydrogen stabilization of shear transformation zones (STZs) in the amorphous structure, while the improved ductility is attributed to the change in the spatial correlation of the STZs.


1970 ◽  
Vol 28 (1) ◽  
pp. 76-77
Author(s):  
S. S. Vasil'ev ◽  
L. M. Velyus ◽  
P. D. Korzh ◽  
V. T. Fomenko

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