Measurement of very small hydrogen content in zirconium alloys by measuring thermal neutron incoherent scattering

2002 ◽  
Vol 74 (0) ◽  
pp. s1710-s1712 ◽  
Author(s):  
Y.N. Choi ◽  
H.S. Oh ◽  
V.T. Em ◽  
V.A. Somenkov ◽  
C.-H. Lee ◽  
...  
Keyword(s):  
Thermal Neutron ◽  
Hydrogen Content ◽  
Zirconium Alloys ◽  
Incoherent Scattering

Observation of Kossel and Kikuchi Lines in Thermal Neutron Incoherent Scattering

2002 ◽  
Vol 88 (6) ◽  
Author(s):  
B. Sur ◽  
R. B. Rogge ◽  
R. P. Hammond ◽  
V. N. P. Anghel ◽  
J. Katsaras
Keyword(s):  
Thermal Neutron ◽  
Incoherent Scattering ◽  
Kikuchi Lines

Formation and Dissolution of Hydride Precipitates in Zirconium Alloys: Crystallographic Orientation Relationships and Stability after Temperature Cycling

2016 ◽  
Vol 879 ◽  
pp. 2330-2335 ◽  
Author(s):  
Egle Conforto ◽  
Stephane Cohendoz ◽  
Cyril Berziou ◽  
Patrick Girault ◽  
Xavier Feaugas
Keyword(s):  
Hydrogen Content ◽  
Hydrogen Diffusion ◽  
Zirconium Alloys ◽  
Temperature Cycling ◽  
Nuclear Industry ◽  
X Rays ◽  
Orientation Relationships ◽  
Hydrogen Distribution ◽  
Cycle Number ◽  
Hydride Phases

Hydride precipitation due to the spontaneous and fast hydrogen diffusion is often pointed as causing embrittlement and rupture in zirconium alloys used in the nuclear industry. Transmission Electron Microscopy (TEM) and X-Rays Diffraction (XRD) have been used to study the precipitation of hydride phases in zirconium alloys as a function of the hydrogen content. The orientation relationships observed between the hydride phase and the substrate were similar to those previously observed in Titanium hydrides grown on Titanium. Dislocation emission from the hydride precipitates has been directly related to the relaxation of the misfit stresses appearing during the transformation. The stability of the hydride phases after several dissolution-reprecipitation cycles have been studied by DSC, TEM and XRD for different total hydrogen content in several alloys. The energy of precipitation observed is lower than that of the dissolution in each case studied. The temperature associated with these two processes slightly increase as a function of the cycle number, as a result of the homogenizing hydrogen distribution in the alloy bulk. The same hydrides phases present before cycling were also observed after 20 cycles. However, transition phases poorer in hydrogen than the dominant one may precipitate at the interface with the substrate. The evolution of these transitions phases with the temperature increase will be investigated by TEM in-situ heating in the next future.

NEUTRON LOGGING OF DRILL HOLES: THE NEUTRON‐NEUTRON METHOD

Geophysics ◽  
1951 ◽  
Vol 16 (4) ◽  
pp. 626-658 ◽  
Author(s):  
C. W. Tittle ◽  
Henry Faul ◽  
Clark Goodman
Keyword(s):  
Thermal Neutron ◽  
Fresh Water ◽  
Hydrogen Content ◽  
Point Of View ◽  
Thermal Neutrons ◽  
Drilling Mud ◽  
Resonance Neutron ◽  
Epithermal Neutrons ◽  
Neutron Method ◽  
Drill Holes

Experiments were performed to determine the distribution of thermal neutrons and of indium resonance neutrons in continuous hydrogenous media and in pipes passing through hydrogenous media. Included in the study were water, brine, mixtures of sand and water, and mixtures of sand and brine. Experiments in a continuous typical barite drilling mud showed that the neutron distributions were essentially the same as in water. Also, from the point of view of these experiments, oil and fresh water are nearly identical. These experiments show that well fluid (and, by inference, cement) imposes serious limitations on the sensitivity and accuracy of the neutron‐neutron logging method. The indium resonance neutron response (or, in general, the intensity of epithermal neutrons) is a more reliable indicator of hydrogen content of the formation than is the thermal neutron response. The neutron‐neutron method of chlorine determination was found to be not sensitive enough to be useful with brines of the concentrations ordinarily found in reservoirs.

Analysis of total hydrogen content in palm oil and palm kernel oil using thermal neutron moderation method

2001 ◽  
Vol 6 (1) ◽  
Author(s):  
E. H.K. Akaho ◽  
S.A. Jonah ◽  
C.P.R. Dagadu ◽  
B.T. Maakuu ◽  
S. Anim-Sampong ◽  
...  
Keyword(s):  
Thermal Neutron ◽  
Palm Oil ◽  
Hydrogen Content ◽  
Palm Kernel ◽  
Neutron Moderation ◽  
Palm Kernel Oil ◽  
Kernel Oil

scholarly journals NANOINDENTATION OF HYDROGEN ENRICHED Zr-1Nb ZIRCONIUM ALLOY NUCLEAR FUEL CLADDINGS

2020 ◽  
Vol 27 ◽  
pp. 155-159
Author(s):  
Ondřej Libera ◽  
Patricie Halodová ◽  
Petra Gávelová ◽  
Jakub Krejčí
Keyword(s):  
Nuclear Fuel ◽  
Hydrogen Content ◽  
Zirconium Alloy ◽  
Nuclear Reactors ◽  
Bulk Material ◽  
Surface Preparation ◽  
Zirconium Alloys ◽  
High Hydrogen ◽  
Operation Conditions ◽  
Zirconium Hydrides

Zirconium alloys are being commonly used as a material of choice for nuclear fuel claddings in water cooled nuclear reactors for decades due to their good corrosion resistance and low neutron absorption. However, the increasing operation conditions of next generation nuclear reactors (Gen-V) in terms of higher temperatures, pressures and higher neutron flux requires evaluation of further Zr cladding usability. The embrittlement of Zr claddings due to hydrogen pickup from reactor coolant is one of the issues for its potential use in Gen-IV reactors. Nanoindentation is an effective tool for analysis of the change of mechanical properties of hydrogen enriched Zr claddings from localised material volume. Zirconium alloy Zr-1Nb (E110) with experimentally induced hydrides was analysed by the means of nanoindentation. Zirconium hydrides were formed in the material after exposure in high temperature water autoclave. The optimized methodology of surface preparation suitable for nanoindentation is described and the resulting surface quality is discussed. The nanoindentation measurements were performed as an array of 10x10 indents across areas with hydrides. Depth dependent hardness and reduced modulus values measured by nanoindentation were compared between the material with no hydrogen content, low hydrogen content (127 ppm H) and high hydrogen content (397 ppm H). Complementary microhardness measurements at HV 0.1 were performed on all materials for bulk material hardness comparison.

Tetragonal Hydride in Lot Hydrogen Content Zircaloy

1970 ◽  
Vol 28 ◽  
pp. 442-443
Author(s):  
O. M. Katz
Keyword(s):  
Neutron Diffraction ◽  
Corrosion Behavior ◽  
Hydrogen Content ◽  
Nuclear Reactor ◽  
Zirconium Alloys ◽  
Cubic Phase ◽  
Face Centered Cubic ◽  
Mechanical Integrity ◽  
The Face ◽  
Face Centered

The mechanical integrity and corrosion behavior in nuclear reactor environments of zirconium alloys can be related to the formation and morphology of intermetallic hydrides which precipitate in them. The nature of these hydrides has been studied and the results summarized in the literature. However, there still seems to be some uncertainty as to the type of hydride which precipitates in low hydrogen content zirconium alloys; i.e., whether it is the face-centered-cubic ∫ phase), designated ZrH1.5, or the face-centered tetragonal hydride, γ‘, of c/a around 1.08. The composition of γ’ was originally placed at ZrH0.5 but was later shown by neutron diffraction to be non-stoichiometric and extending to ZrH.

Impact of Hydrogen Content on the Thermal Stability of Hydride Phases in Zirconium Alloys

2018 ◽  
Vol 941 ◽  
pp. 1318-1323
Author(s):  
Egle Conforto ◽  
Patrick Girault ◽  
Cyril Berziou ◽  
Guillaume Lotte ◽  
Rémy Milet ◽  
...  
Keyword(s):  
Hydrogen Content ◽  
Hydrogen Diffusion ◽  
Zirconium Alloys ◽  
Nuclear Industry ◽  
Orientation Relationships ◽  
Hydrogen Atoms ◽  
Diffusion Controlled ◽  
Zirconium Hydrides ◽  
Thermal Stability Of

The fast and spontaneous hydrogen diffusion in HCP structures leads to the hydride precipitation. It is often pointed as causing embrittlement and rupture in zirconium alloys for applications in the nuclear industry. In our previous works TEM, DSC, SEM-EBSD and XRD were used to study the hydride stability after many precipitation-dissolution thermal cycles as well as the crystallographic hydride phase nature and the hydride-substrate crystallographic orientation relationships as a function of the hydrogen content. Results showed that the evolution of the dissolution and precipitation energies is correlated to the concentration of hydrogen atoms available to reprecipitate, which is submitted to a diffusion controlled by the misfit dislocation migration. In the present workin-situTEM thermal cycling was performed in order to locally investigate the crystallographic stability of zirconium hydrides of different structures after many dissolution-reprecipitation cycles.

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

2021 ◽  
Vol 9 (4) ◽  
pp. 451-454
Keyword(s):  
Mechanical Properties ◽  
Thermal Neutron ◽  
Present Article ◽  
Hydrogen Content ◽  
Neutron Absorption ◽  
After Effect ◽  
Alpha Beta

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

Neutron Incoherent Scattering Measurements on Hydrogen-Charged Zircaloy-4

2007 ◽  
Vol 539-543 ◽  
pp. 1443-1448 ◽  
Author(s):  
E. Garlea ◽  
V.O. Garlea ◽  
Hahn Choo ◽  
C.R. Hubbard ◽  
Peter K. Liaw
Keyword(s):  
Hydrogen Content ◽  
Coherent Scattering ◽  
Incoherent Scattering ◽  
Zirconium Hydride ◽  
Face Centered Cubic ◽  
Hydrogen Atoms ◽  
Scattering Measurements ◽  
The Face ◽  
Argon Mixture ◽  
Face Centered

Neutron incoherent scattering measurements were conducted on Zircaloy-4 round bars. The specimens were charged in a tube furnace at 430 °C, using a 12.5 vol. % hydrogen in an argon mixture for 30, 60, and 90 minutes at 13.8 kPa pressure. The volume-average neutron diffraction measurements showed the presence of the face-centered-cubic delta zirconium hydride (δ-ZrH2) phase in the hydrogenated specimens. The assessment of the background in the diffraction profiles due to the incoherent scattering from the hydrogen atoms was carried out by performing inelastic scans around zero energy transfer and at a fixed two-theta value for which there was only flat background and no coherent scattering. To estimate the relative amount of hydrogen in the Zircaloy-4 samples, the increase in incoherent scattering intensities with hydrogen content was calibrated using samples for which the hydrogen content was known. Measurement of the background scattering from locations within the round bar was also performed to map the distribution of hydrogen content.

Sign in / Sign up

Export Citation Format

Share Document