The effect of neutron and gamma irradiation on the dislocation relaxation peak in silver

Summary The internal-friction spectrum has been determined in extremely pure polycrystalline silver crystals after being subjected to neutron and gamma irradiation. The spectra obtained for an applied frequency of 10 MHz show that the mechanical losses due to dislocation relaxation decrease as the doses of neutron and gamma radiation increase. The effect of gamma radiation was found to be more significant than that of neutron irradiation. The relationship between damping neutron and gamma dose was found to be of the formQ _max ⁻¹ α ΛD ^η, where η is equal to −1.2 for neutron and −1.45 for gamma irradiation. The variations of the peak height and width, and temperature of the dislocation relaxation peak as functions of neutron and gamma doses are explained in terms of the pair-kink formation model.     

Drastic effects of fast neutrons and γ-irradiation on the DC conductivity of Co-, Ni-, Mn- and Ag-gelatin doped films

The effect of fast neutron fluencies and γ-rays on the DC conductivity, ln(σ), for pure gelatin and that doped with 5, 10, and 15 wt% of CoCl₂ · 6H₂O, and 5 wt% of NiCl₂ · 6H₂O, MnCl₂ · 2H₂O and AgNO₃ has been respectively investigated at different temperatures. Fast neutron fluencies and γ-rays doses are set from 7.60 × 10⁵ to 0.50 × 10⁹ N/cm², and 0.25 up to 1.50 Gy, respectively. The calculated values of activation energies (E_a) are found to be dependent on the radiation doses. The conductivity of gelatin samples shows an interesting behavior, which depends on the dopant Co concentration and the exposure dose. DC conductivity of the investigated samples reveals that the ionic conduction has been established at higher temperatures and fast neutron fluencies and γ-rays doses, while the electronic one plays an important role at lower temperatures. This has been related to the crosslinking formations as a result of the interaction between the exposure dose and gelatin sample. The attained results suggest strongly the applicability of these materials in dosimetry.     

The optical and electrical effects of high concentrations of defects in irradiated crystalline gallium arsenide

The damage produced by fast neutron irradiation of gallium arsenide has been studied by a number of techniques. The electrical resistivity, which increases with dose at low doses to semi-insulating values, shows a remarkable, specimen-independent decrease for doses greater than 10¹⁷ n cm^-2 from values of ca. 10⁹ Ω cm to 3 Ω cm for the highest dose of 1.5 × 10²⁰ n cm^-2. In this high dose region the temperature dependence of the resistivity at low temperatures is given by exp [b/T ^1/4] and it is suggested that in this highly disordered state conduction occurs by tunnel-assisted hopping between defect levels in the band gap. The presence of such levels is indicated by the strong optical absorption tail which is produced from 0.1 eV to the crystalline edge at 1.5 eV.

Although at the highest doses the samples contain a high degree of disorder, X-ray diffraction shows that they are basically crystalline. Lattice parameter determinations show that it increases with dose, linearly at first, then tending to saturation for doses above 2 × 10¹⁸ n cm^-2. The dose dependence of the lattice parameter is the same as that of the integrated optical absorption and both effects may be expected to relate to the total defect concentrations.

The existence of small-angle neutron scattering at the highest dose shows that the defects are not uniformly distributed. It is shown that this state is the high dose manifestation of the production of defects by each primary knock-on atom in fairly localized regions. The overlap of the wings of these regions for doses greater than 10¹⁷ n cm^-2 provides a conducting path and a fairly constant b value with dose, while the resistivity decreases rapidly. The total defect concentration, which is heavily weighted to the central regions of the individually damaged volumes, does not show overlap until a higher dose, as observed for the optical absorption and lattice parameter.

Estimates of the total defect concentration have been obtained by measuring the total diffuse neutron scattering as well as from the small-angle scattering results. It is shown that each primary knock-on produces ca. 10³ atomic displacements. This means that the amount of damage in gallium arsenide is close to that predicted by radiation damage theory.

Measurements of photoconductivity show that the sharp photoconductivity edge is eliminated at quite low doses. At high doses the photoconductivity becomes very small and is much less than in unirradiated samples of similar resistivity. It appears that the ionized state lifetime of photo-induced carriers is very small in the high dose state.

The effects anneal more or less completely after heating to 700°C. The hopping conductivity effect anneals between room temperature and 400°C and the remaining electrical effects between 500 and 600°C. The optical effects anneal more or less continuously throughout the temperature range up to 700°C.

It is shown that the doses at which the tunnel-assisted hopping sets in are consistent with similar effects recently observed in ion implantation. We suggest that a similar mechanism applies in implanted layers for ion doses greater than 10¹²–10¹³ ions cm^-2.

Density measurements show an expansion identical with the lattice parameter expansion and indicate an expansion of 2.93 ų per defect. This is relatively small and is consistent with the tentative conclusion from the neutron-scattering data that the main defect is the close interstitial-vacancy pair in which the strain is minimized by being of opposite sign around each component.     

An investigation into the accuracy of the albedo dosimeter DVGN-01 in measuring personnel irradiation doses in the fields of neutron radiation at nuclear power installations of the joint institute for nuclear research

The calculated results of research into the accuracy of an individual albedo dosimeter DVGN-01 as it corresponds to the personal equivalent dose for neutrons H _p (10) and to the effective dose for neutrons E _eff in the neutron fields at Joint Institute for Nuclear Research Nuclear Power Installations (JNPI) upon different geometries of irradiations are presented. It has been shown that correction coefficients are required for the specific estimation of doses by the dosimeter. These coefficients were calculated using the energy sensitivity curve of the dosimeter and the known neutron spectra at JNPI. By using the correction factors, the uncertainties of both doses will not exceed the limits given to the personnel according to the standards.     

Discussion on sources of uncertainty for two TLD albedo dosimetry systems in a comparison of individual monitors in a reference 241Am–Be field

Under standard conditions, several studies assess uncertainty values for individual dosimetry for photons, but seldom for neutrons. The Thermoluminescent Dosimetry Laboratory (LDT) of the Instituto de Radioproteção e Dosimetria (IRD), Brazil, has been running a neutron individual monitoring service using two different albedo monitors. This paper presents a study of the contribution of relevant sources of uncertainty for neutron dose evaluation, for both systems (called System 1 and System 2), using a reference ²⁴¹Am–Be field, at normal incidence. The combined and expanded uncertainties were calculated using GUM methodology and follows RP160 from the European Commission. This methodology was applied to calculate the uncertainties associated with the LDT assessment of neutron doses in the First Brazilian National Comparison on Measurements for Neutron Individual Monitors. The LDT participated in this comparison with its two systems, both presenting satisfactory performance. For System 1, at low neutron doses, the reproducibility of the apparent neutron dose is the more relevant source of uncertainty. However, for higher doses, the neutron calibration factor, NCF, becomes more important. For System 2, NCF is the main source of uncertainty for low and high doses. For occupational doses, the uncertainty will be much higher due to the need of additional correction factors, which depend on stray neutron field.     

Magnetic Properties of Neutron-Irradiated RPV Steel by Mössbauer Spectroscopy

The neutron irradiated reactor pressure vessel (RPV) steels at various doses of 010¹⁸ n/cm² have been studied with Mössbauer, X-ray diffraction, and VSM. The Mössbauer data show that the value of a magnetic hyperfine field of Fe atom that exists at the martensite is 330 kOe at site 1, and 305 kOe, at site 2. At room temperature, the total absorption area of Mössbauer spectra with respect to irradiation of neutron is constant for the dose of 010¹⁶ n/cm², while over the dose of 10¹⁷ cm² the absorption area decreases rapidly. But the doublet area for the dose of 010¹⁶ n/cm² is constant, while over the dose of 10¹⁷ cm² it increases with an increase in the fluence level of neutron. The value of IS and QS at site 1,2 varied slightly with an increase in the fluence level of neutron. However, at a doublet site existing Fe³⁺ state, over the dose of 10¹⁷ cm², the values of IS and QS increase with an increase in the fluence level of neutron. Note that over the dose of 10¹⁷ n/cm² the neutron irradiated sample loses crystal structure slowly. The coercivity and remanence of the neutron irradiated samples do not change significantly. But the maximum induction decreases by 5% at 10¹⁸ n/cm², us compared with that of the as-received sample.     

Effects of radiations on the characteristics of alpha and fission tracks in CR-39 detectors

Abstract

The effects of neutron, gamma and alpha radiations on the alpha and fission fragment tracks registration and revelation properties of CR-39 detectors (CR-39 and CR-39(DOP) were studied. It was found that the ratio of the bulk etch rate of irradiated to unirradiated (V_G(irr.)/V_G(unirr.) detectors is linearly dependent on dose. An exponential decrease in fission track densities with increase in neutron fluence was observed. The ratio of V_G(irr.)/V_G(unirr.) was found to be high in CR-39 than that in CR-39(DOP) exposed to the same reactor neutron fluence. The decrease in fission track densities with increase in neutron fluence was observed to be faster in CR-39 than in CR-39(DOP). This indicates that doping with dioctyl phthalate improves the radiation resistance of CR-39 detectors. It was observed that in detectors exposed to an alpha flux of the order of 9.36 × 10⁶ / cm², the fission track density was reduced by 11% and thereafter it remained constant. The results also indicate that thermal neutron fluence up to 7.01 ×10¹¹ neutrons/cm² does not affect the alpha and fission track densities. I.R. spectra were also studied to find out the nature of chemical changes produced by these radiations on CR-39.     

High-dose reactor irradiation of iron at 4.6 K: Dose and recovery curves of electrical resistivity

The increase of residual resistivity ?_o of iron during reactor irradiation at 4.6 K has been studied up to a fast neutron dose as high as 1.07 × 10¹⁹ n/cm². The outstanding result is a negative curvature of the differentiated dose curve which probably has to do with the ferromagnetic nature of Fe. Isochronal annealing showed pronounced stages I and II but only little recovery between 300 and 400 K (formerly called stage III).     

The relative biological effectiveness of a high energy neutron beam for micronuclei induction in T-lymphocytes of different individuals

In assessing the radiation risk of personnel exposed to cosmic radiation fields as it pertains to radiological damage during travel in civilian aircrafts, it is particularly important to know the relative biological effectiveness (RBE) for high energy neutrons. It has been the subject of numerous investigations in recent years using different neutron energies and cytogenetic examinations. Variations in the radiosensitivity of white blood cells for different individuals are likely to influence the estimate of the relative biological effectiveness for high energy neutrons. This as such observations have been noted in the response of different cancer cell lines with varying inherent sensitivities. In this work the radiosensitivities of T-lymphocytes of different individuals to the p(66)/Be neutron beam at iThemba LABS were measured using micronuclei formations and compared to that noted following exposure to ⁶⁰Co γ-rays. The principle objective of this investigation was to establish if a relationship between neutron RBE and variation in biological response to ⁶⁰Co γ-rays for lymphocytes from different individuals could be determined. Peripheral blood samples were collected from four healthy donors and isolated lymphocytes were exposed to different doses of ⁶⁰Co γ-rays (1–5 Gy) and p(66)/Be neutrons (0.5–2.5 Gy). One sample per donor was not exposed to radiation and served as a control. Lymphocytes were stimulated using PHA and cultured to induce micronuclei in cytokinesis-blocked cells. Micronuclei yields were numerated using fluorescent microscopy. Radiosensitivities and RBE values were calculated from the fitted parameters describing the micronuclei frequency dose response data. Dissimilar dose response curves for different donors were observed reflecting varying inherent sensitivities to both neutron and gamma radiation. A clear reduction in the dose limiting RBE_M is noted for donors with lymphocytes more sensitive to γ-rays (p = 0.032, R² = 0.94). Unlike observations made with different cancer cell lines exposed to the same clinical neutron beam, the variations in neutron RBE observed in T-lymphocytes of different individuals is related to the cellular radioresistance to photons.     

In-phantom neutron dose distribution for bladder cancer cases treated with high-energy photons

This work presents an estimation of the neutron dose distribution for common bladder cancer cases treated with high-energy photons of 15 MV therapy accelerators. Neutron doses were measured in an Alderson phantom, using TLD 700 and 600 thermoluminescence dosimeters, resembling bladder cancer cases treated with high-energy photons from 15 MV LINAC and having a treatment plan using the four-field pelvic box technique. Thermal neutron dose distribution in the target area and the surrounding tissue was estimated. The sensitivity of all detectors for both gamma and neutrons was estimated and used for correction of the TL reading. TLD detectors were irradiated with a Co⁶⁰ gamma standard source and thermal neutrons at the irradiation facility of the National Institute for Standards (NIS). The TL to dose conversion factor was estimated in terms of both Co⁶⁰ neutron equivalent dose and thermal neutron dose. The dose distribution of photo-neutrons throughout each target was estimated and presented in three-dimensional charts and isodose curves. The distribution was found to be non-isotropic through the target. It varied from a minimum of 0.23 mSv/h to a maximum of 2.07 mSv/h at 6 cm off-axis. The mean neutron dose equivalent was found to be 0.63 mSv/h, which agrees with other published literature. The estimated average neutron equivalent to the bladder per administered therapeutic dose was found to be 0.39 mSv Gy^?1, which is also in good agreement with published literature. As a consequence of a complete therapeutic treatment of 50 Gy high-energy photons at 15 MV, the total thermal neutron equivalent dose to the abdomen was found to be about 0.012 Sv.     

Investigations of two-level tunneling systems in n-irradiated quartz by diffuse x-ray scattering

Abstract

Recent observation of the acoustic saturation and of phonon echoes in crystalline quartz after light irradiation with fast neutrons indicates that there are the same low-energy atomic tunnelling systems as in Si0₂ glass.

We report measurements of the diffuse X-ray scattering and of the lattice parameter change from neutron irradiated quartz single crystals studying the strength and symmetry of strain defects and their local correlations. For dose 3 × 10¹⁸ n/cm² the diffuse scattering close to the Bragg peaks together with the lattice parameter change shows that the neutrons create defective regions with a volume change of 29 mean atomic volumes. The distortion field of these regions shows no high symmetry. The radius of the heavily strained region is ～ 10 Å. For higher doses the regions grow a little bit but mainly new defective regions are built.

According to the various volume fractions of defective regions at various doses the first strong amorphous halo at about K≈ 1.5 A^?1 was detected. Since this amorphous scattering is isotropic and during annealing the regions disappear mainly without changing their size we are led to the conclusion that the defective regions are glass-like in nature. So the size of the tunnelling system has to be smaller than 20 Å.     

Effect of ionizing radiation on the dielectric characteristics of TlInS2 and TlGaS2 single crystals

The dependences of the permittivity and electrical conductivity of TlInS₂ and TlGaS₂ single crystals on the temperature and electron beam irradiation dose have been studied. It has been established that, as the electron irradiation dose increases, the electrical conductivity σ significantly increases, whereas the permittivity ? decreases over the entire temperature range covered (80–320 K). It has been shown that anomalies in the form of maxima in the temperature dependences σ(T) and ?(T) are observed in the regions characteristic of phase transitions in TlInS₂. Irradiation of the TlInS₂ and TlGaS₂ crystals with electrons to doses of 10¹⁵ and 10¹⁶ cm^?2 does not affect their phase transition temperatures. The dispersion curves of the permittivity ? of the TlGaS₂ crystal have been constructed.     

Application of 10B counter with moderator for neutron ambient dose equivalent measurement during radiation monitoring at joint institute for nuclear research

The results of an investigation into the possibility of applying a device based on a ¹⁰B neutron counter (CHM-14) with a polyethylene moderator as the dosimeter of neutron ambient dose equivalent H*(10) in radiation fields of nuclear physics installations at the Joint Institute for Nuclear Research (JINR) are presented. It is shown that the device can be used as the dosimeter of this quantity in the neutron energy range from 0.4 eV to 20 MeV with an error no larger than 30% due to the difference between the energy dependence of its response and the energy dependence of the neutron ambient dose equivalent. Applying the correction coefficients allows one to extend the energy range of neutron dose H*(10) measurement to hundreds MeV. The error due to the anisotropy of the device response does not exceed 35%.     

Assessment of fast and thermal neutron ambient dose equivalents around the KFUPM neutron source storage area using nuclear track detectors

A set of five ²⁴¹Am–Be neutron sources are utilized in research and teaching at King Fahd University of Petroleum and Minerals (KFUPM). Three of these sources have an activity of 16 Ci each and the other two are of 5 Ci each. A well-shielded storage area was designed for these sources. The aim of the study is to check the effectiveness of shielding of the KFUPM neutron source storage area. Poly allyl diglycol carbonate (PADC) Nuclear track detectors (NTDs) based fast and thermal neutron area passive dosimeters have been utilized side by side for 33 days to assess accumulated low ambient dose equivalents of fast and thermal neutrons at 30 different locations around the source storage area and adjacent rooms. Fast neutron measurements have been carried out using bare NTDs, which register fast neutrons through recoils of protons, in the detector material. NTDs were mounted with lithium tetra borate (Li₂B₄O₇) converters on their surfaces for thermal neutron detection via and nuclear reactions. The calibration factors of NTD both for fast and thermal neutron area passive dosimeters were determined using thermoluminescent dosimeters (TLD) with and without a polyethylene moderator. The calibration factors for fast and thermal neutron area passive dosimeters were found to be 1.33 proton tracks and 31.5 alpha tracks , respectively. The results show variations of accumulated dose with the locations around the storage area. The fast neutron dose equivalents rates varied from as low as up to whereas those for thermal neutron ranged from as low as up to . The study indicates that the area passive neutron dosimeter was able to detect dose rates as low as 7 and from accumulated dose for thermal and fast neutrons, respectively, which were not possible to detect with the available active neutron dosimeters.     

Preliminary TL Studies of K2GdF5:Dy3+ exposed to photon and neutron radiation fields

Results of the investigation concerning thermoluminescence (TL) responses to X, gamma and neutron radiation fields for crystals of complex fluoride K₂GdF₅ undoped and doped with varying concentrations of Dy³⁺ ions are presented. Crystals doped with 5.0 at% Dy³⁺ have shown the most efficient TL response, with a linear response to doses for all the radiation fields. In the X rays range, the maximum TL response has been found to be 15 times more than the response for gamma. The fast and thermal neutron TL outputs were evaluated for K₂Gd_0.95Y_0.05F₅ and the contribution of the gamma component in the TL curve was estimated.     

Neutron radiation on tin anodes of lithium-ion batteries

Abstract

The operating durability of lithium-ion batteries is a principal problem in universe exploration or rescuing work in the nuclear radiation area. In the study, the neutron irradiation experiments were conducted on film-tin electrodes using the radiation dose of 10¹¹, 10¹², 10¹³ and 10¹⁴?n?cm^?2, respectively. The results show that the particle size grows with the increasing radiation does by atomic force microscopy (AFM) and scanning electron microscope (SEM). In addition, the degressive trend of specific capacity of tin anodes after neutron radiations increases with the increasing radiation dose. The fade of electrochemical performances may be attributed to the increasing particle size and defects induced by neutron radiation.     

Neutron ambient dose equivalent from 5 MeV/u 10,11B, 12,13C and 16,18O projectiles incident on a thick Al target

The neutron ambient dose equivalent has been measured from ¹⁰B, ¹¹B, ¹²C, ¹³C, ¹⁶O and ¹⁸O projectiles of energy 5 MeV/amu incident on a thick Al target at 0°, 30°, 60° and 90° with respect to the beam direction using a conventional dose equivalent meter. The calculated results obtained using previously reported empirical relations do not reproduce the experimental data. The results obtained from the PACE nuclear reaction code are closer to the experimental data as compared to the various empirical expressions. The ratio of the increase in the dose rates when the projectile is changed from the lighter to the heavier isotopes is fairly reproduced by most of the empirical formulations and the PACE code. A previously reported relation for the slope parameter is used to predict the directional distribution of the neutron dose for the projectiles used in this study. The calculated doses are lower than the experimental results in the forward directions but agree within the uncertainties at the backward directions. A new set of projectile-based parameters have been derived from the present experimental data which can be used in an empirical formulation.     

Influence of neutron irradiation and temperature on the electric conductivity of SiO2 nanoparticles

At different frequency range it has been studied the influence of temperature and amount of falling neutrons on nano SiO₂ irradiated with neutrons. It has been revealed that it is generated additional electroactive radiation defects under the influence of rays omitted from activation products or direct neutron. Thus, the change of neutron flux at 6.7 × 10¹⁷ ∼ 2.7 × 10¹⁸ cm⁻² s⁻¹ range increases the electric conductivity of nano SiO₂ for approximately 30 times. It has been revealed two temperature ranges at temperature dependence of non-irradiated sample and three temperature ranges at a neutron irradiated-sample. It has been put forward the mechanism that explains the obtained results.     

Fermi sea effects on pion and kaon properties in the Nambu-Jona-Lasinio model

We study modifications of hadronic properties in dense nuclear and neutron matter, in the context of a generalized three-flavor Nambu-Jona-Lasinio model, focussing mainly on Fermi sea effects. In symmetric nuclear matter, we observe the splitting between K^± and the occurrence of a low-lying K⁻ branch at baryonic densities around 0.4 times normal nuclear matter density ϱ₀. This branch is not significantly affected by the inclusion of strange matter in the medium while the flavor asymmetry is preserved. A similar π⁺ branch is found in neutron matter at neutron densities around 0.3ϱ₀. These low-lying modes are particle-hole excitations of the Fermi sea and decrease smoothly with density. In any case, the vacuum does not exhibit signs of instability associated with boson condensation.     

Doping and radiation damage profiles of P+ ions implanted in silicon along the [110] axis

Several doses of 200 KeV phosphorus ions have been implanted under channeling conditions along the [110] direction in silicon.

Range distribution has been determined for the three implant doses 10¹³, 10¹⁴, 10¹⁵ P⁺/cm² both with the electrical measurements and the neutron activation techniques.

The radiation damage distribution has been determined both with 290 KeV proton back-scattering analysis and with transmission electron microscopy (TEM) observations.

Good agreement has been found between electrical and neutron activation profiles in the samples where 100% of the implanted dose had been electrically activated by means of annealing.

Carrier concentration profiles, from samples implanted with 10¹⁵ P⁺/cm², determined after two different annealing temperatures (500°C and 700°C) have bcen compared with the radiation damage distribution and a correlation between damage and phosphorus electrical activation process seems to be possible.

Maximum damage peak, as determined by back-scattering analysis, shifts from ～0.4 μ depth in the lower dose(5 × 10¹⁴ P⁺/cm²), to ～0.22 pm depth in the higher implanted dose (4 × 10¹⁵ P⁺/cm²). Damage distribution of phosphorus ions random implanted in the same experimental conditions shows 3 peak at ～0.2 μn depth.

In accordance with the back-scattering analysis, T.E.M. observations on 10¹⁵P⁺/cm² implanted samples show the presence of amorphous regions at depth between 0.25 and 0.5 μm from the surface. In the most damaged layer ～0.3μm in depth, a surface density of ～10¹²/cm² amorphous regions 25-50 A diameter was observed.