Measurement of the plastic scintillator response in the magnetic field

We present the results of measurements of the light yield dependencies for the plastic scintillators on magnetic field value and orientation. The magnetic field value was changed from 0 up to 3.8 T. Scintillators were irradiated by electrons (¹³⁷Cs and ²⁰⁷Bi) and by alpha-particles (²⁴¹Am). The detected light spectra in the electron irradiating cases show two dependencies: the first one is dependence on the magnetic field value only and the second-light output is dependent on the magnetic field orientation when the radioactive source is outside of the scintillator. The value and behavior of the first dependence agree with data published earlier.

Under alpha-particle irradiation the light output does not depend on the magnetic field value and orientation practically.     

Investigation of CdTex and Cd1-xZnxTe Schottky Barrier Diode Structure Based γ-Ray Detectors

Cadmium Telluride (CdTe) and Cadmium Zinc Telluride (CdZnTe) based detectors have been developed for hard X-ray and γ -ray detection. These semiconducting materials have high resistivity because of the wide bandgap and also have high photon absorption efficiency because of the large atomic number (Z_Cd = 48, Z_Te = 52). CdTe and CdZnTe substrates (7 mm × 9 mm × 0.5 mm) with different stoichiometry were taken for the fabrication of γ-ray detectors. The substrate was prepared by polishing the bulk crystals grown by the rotational Bridgman method. Crystals with maximum electrical resistivity were grown in this way. For fabrication of Schottky barrier diode structures, the Schottky contacts were made by electroless deposition for gold (Au) and thermal evaporation for Indium (In). The Au/CdTe/In and Au/CdZnTe/In Schottky barrier diodes were linked to the charge sensitive preamplifier by gold wires. Then, I-V measurement and detector efficiency like charge collection performance with energy resolutions were analyzed at room temperature by using ⁵⁷Co and ¹³⁷Cs gamma sources. The good energy resolutions of ⁵⁷Co (122 KeV) and ¹³⁷Cs (662 KeV) sources are obtained for both CdTe and CdZnTe diode detectors.     

Comparison of optimised germanium gamma spectrometry and multicollector inductively coupled plasma mass spectrometry for the determination of Cs, Cs and Eu single ratios in highly burnt UO2

Non-destructive and destructive methods have been compared to validate their corresponding assessed accuracies in the measurement of ¹³⁴Cs/¹³⁷Cs and ¹⁵⁴Eu/¹³⁷Cs isotopic concentration ratios in four spent UO₂ fuel samples with very high (52 and 71 GWd/t) and ultra-high (91 and 126 GWd/t) burnup values, and about 10 (in the first three samples) and 4 years (in the latter sample) cooling time. The non-destructive technique tested was high-resolution gamma spectrometry using a high-purity germanium detector (HPGe) and a special tomographic station for the handling of highly radioactive 400 mm spent fuel segments that included a tungsten collimator, lead filter (to enhance the signal to Compton background ratio and reduce the dead time) and paraffin wax (to reduce neutron damage). The non-destructive determination of these isotopic concentration ratios has been particularly challenging for these segments because of the need to properly derive non-Gaussian gamma-peak areas and subtract the background from perturbing capture gammas produced by the intrinsic high-intensity neutron emissions from the spent fuel. Additionally, the activity distribution within each pin was determined tomographically to correct appropriately for self-attenuation and geometrical effects. The ratios obtained non-destructively showed a 1σ statistical error in the range 1.9–2.9%. The destructive technique used was a high-performance liquid chromatographic separation system, combined online to a multicollector inductively coupled plasma mass spectrometer (HPLC-MC-ICP-MS), for the analysis of dissolved fuel solutions. During the mass spectrometric analyses, special care was taken in the optimisation of the chromatographic separation for Eu and the interfering element Gd, as also in the mathematical correction of the ¹⁵⁴Gd background from the ¹⁵⁴Eu signal. The ratios obtained destructively are considerably more precise (1σ statistical error in the range 0.4–0.8% for most of the samples, but up to 2.8% for one sample). The HPGe gamma spectrometry can achieve a high degree of accuracy (agreement with HPLC-MC-ICP-MS within a few percent), only by virtue of the optimised setup, and the refined measurement strategy and data treatment employed.     

Activity concentration of a solution of Cs: An international comparison

Participants in 19 national and international laboratories measured the activity concentration of samples of a solution of ¹³⁷Cs by means of efficiency tracing. Samples of a ¹³⁴Cs tracer solution, which had been standardized by ionization-chamber measurements in the framework of the international reference system, were distributed as well. The composition of the solutions, the preparation of sources and the counting equipment used are described briefly and an outline of the efficiency-tracing method is given. Results and uncertainties are presented in a table and a graph. The mean activity concentration, with its combined uncertainty (1σ), on the reference date was (604.1 ± 4.0) kBq g⁻¹.     

γ-ray energies for calibration from the decay of Tb, Hf + Lu, and Am

The energies of a few γ-rays from 23 to 125 keV from the decay of the radioisotopes ¹⁶¹Tb, ¹⁷²Hf+ ¹⁷²Lu, and ²⁴¹Am have been determined. These energies were obtained from measurements of differences in the energies of closely spaced lines. The statistical components of the uncertainties of these energy differences range from 0.1 to 1.9 eV. Since it is a long-lived nuclide, these results should make ¹⁷²Hf, which has γ-rays from 23 to 125 keV, a useful energy calibration source. For ²⁴¹Am, our value of 59.5412(2) for this widely used line differs from the previously accepted value of 59.537(1) keV.     

A novel gamma-ray imaging concept using “edge-on” microchannel plate detector

The “edge-on” illuminated microchannel plate (MCP) position-sensitive detector (PSD) is used for gamma-ray imaging for the first time. The superior position resolution of the MCP is combined with high detection efficiency due to the “edge-on” illumination mode. The results of imaging a 15 μCi ¹³⁷Cs source (662 keV quantum energy) are presented.     

Precision energy and intensity measurements for γ transitions from Cs decay

The precision energies and relative intensities of 11 γ transitions from the decay of ¹³⁴Cs have been determined. ¹⁹²Ir, ²²⁸Th, ¹³⁷Cs, ^110mAg, ⁶⁰Co, and ²⁰⁷Bi served as energy calibration standards, and ¹⁵²Eu and ¹⁹²Ir as relative intensity calibration standards. Special care was taken in the analysis of data for the weaker transitions. The results are incorporated into a self-consistent decay scheme.     

富集10B的Ce:Li6Lu(10BO3)3晶体生长及其闪烁性能

为了提高中子探测效率, 以富集¹⁰B的H₃¹⁰BO₃为原料, 通过提拉法生长了富集¹⁰B的Ce:Li₆Lu(¹⁰BO₃)₃晶体。X射线激发发射光谱测试表明: 其发光峰位于360~480 nm, 属于Ce³⁺离子典型的5d - 4f跃迁发光, 其闪烁发光效率为BGO晶体的3.9倍。在350 nm紫外光和¹³⁷Cs所发出的662 keV的γ射线激发下测得的衰减时间分别为21.0 ns 和31.7 ns, 在¹³⁷Cs辐射源激发下所测得的相对光输出是CsI(Tl)晶体的20%, 能量分辨率为9.7%。在慢化²⁵²Cf中子源激发下可以观测到明显的中子全能峰, 其能量分辨率为33%。上述研究结果表明, Ce:Li₆Lu(¹⁰BO₃)₃晶体具有较高的闪烁效率、快的衰减时间和良好的中子探测效率, 是一种具有应用前景的中子探测用闪烁晶体。     

Detection of γ-rays with a 3.5 l liquid xenon ionization chamber triggered by the primary scintillation light

A gridded ionization chamber with a drift length of 4.5 cm and a total volume of 3.5 l, was operated with high-purity liquid xenon and extensively tested with γ-rays from ¹³⁷Cs, ²²Na and ⁶⁰Co radioactive sources. An electron lifetime in excess of 1 ms was inferred from two independent measurements. The electric field dependence of the collected charge and energy resolution was studied in the range 0.1–4 kV/cm, for different γ-ray energies. With an electric field of 4 kV/cm, the spectral performance of the detector is consistent with an energy resolution of 5.9% at 1 MeV, scaling with energy as E^−0.5. The chamber was also used to detect the primary scintillation light produced by γ-ray interactions in liquid xenon. The light signal was successfully used to trigger the acquisition of the charge signal with a FADC readout. A trigger efficiency of 85% was measured at 662 keV.     

Leakage tests for Am solid sources used for liquid xenon detector monitoring

Experimental tests are described to check solid ²⁴¹Am radioactive sources used to monitor operation of liquid xenon detectors. In particular, radioactive leakage was tested in extreme temperature conditions following immersion in liquid nitrogen for different time periods. No radioactivity loss was detected from the sources considered. The paper describes the source characteristics, test methods and results obtained.     

Tungsten alloys as radiation protection materials

The radiation shielding effects of some tungsten alloys were evaluated using ¹³³Ba(356 keV) and ¹³⁷Cs(660 keV)γ-ray sources. Tungsten carbide had about the same effect as the commonly used lead, while tungsten-copper alloy gave as good a performance as tungsten. The results of transmittance measurements for these materials, as well as of their Monte-Carlo simulation, are reported.     

Calculation of efficiency functions in 4π β-γ counting

An attempt is made to calculate an efficiency function applicable to 4πβ-γ coincidence measurements as the first stage of evaluating the order of the polynomial of the fitting function. For this purpose, the β-ray energy spectra and self-absorptions of spherical particle sources are calculated by the Monte Carlo simulation under the continuous slowing down approximation. On the other hand, it is shown that three sets of absorption coefficients and partial intensity ratios corresponding to a β-ray group give analytically the self-absorption for the same particle sources. Finally, we show that the efficiency functions applicable to ⁵⁹Fe and ¹³⁴Cs are easily obtained by using the energy spectra or self-absorptions.     

Double atomic-field bremsstrahlung from thick targets

Measurements of the two-photon coincidence rate from 84 keV electrons from a ¹⁰⁹Cd source on thick targets of Ag, Au, and Pb are compared with a thick-target double atomic-field bremsstrahlung (TBD) model. Each photon energy range was 32–52 keV. The target thickness ranged from 3 to 30 mg/cm². Results for the thick-target single-bremsstrahlung (TSB) energy spectrum for 64 keV electrons in coincidence with the 22 keV X-ray from the source will also be compared with the TSB theory.     

Standing-wave solutions of the Enneper (sine-Gordon) equation

The present paper investigates the real solutions of the partial differential equations (∂²ω/∂u²) − (∂²ω/∂ν²) = sin ω (Enneper or sine-Gordon equation) that are of the FORM = F(|₁(u) · |₂(ν)). In the application of the Enneper equations to crystal physics such solutions may represent standing waves. A complete classification of these solutions and its degenerate cases is given.     

Position-sensitive superheated-liquid-droplet neutron dosimeter

The one-dimensional (1D) position-sensitive superheated-liquid-droplet dosimeter (SLDD) has been fabricated and tested in the laboratory. The 1D SLDD is fabricated from a 9.525-mm OD, 6.35-mm ID, 20-cm long, Plexiglas-walled tube filled with a mixture of superheated-liquid Freon droplets and host medium glycerol. Washer-shaped piezoelectric acoustic transducers are positioned at both ends of the tube; they determine the number and positions of the acoustic events when the superheated-liquid droplets evaporate upon neutron irradiation. The SLDD is irradiated with the ¹³⁷Cs and ⁶⁰Co γ-sources, as well as ²⁵²Cf neutron source to test for its radiation response and spatial resolution. The SLDD based on the Freon-134a superheated-liquid droplets operating at 20°C and 1 atm is found to be ideal for measuring absorbed neutron dose. This study also proves that the positions of the radiation-induced nucleation acoustic events can be linearly determined from the differences in the transmission times received by the acoustic transducers on the 1D SLDD. The spatial resolution of the neutron depth-dose is 1 mm due the finite response time (1 μs) of the piezoelectric acoustic transducers.     

Composite detector for mixed radiations based on CsI(Tl) and dispersions of small ZnSe(Te) crystals

A new large area detector of high-energy X-ray and β-radiation has been designed and studied. A composite material based on small-crystalline ZnSe(Te) was applied onto the wide surface of a light guide. An experimental specimen has been prepared, which showed β-sensitivity . The spectrograms of a ⁹⁰Sr+⁹⁰Y β-source obtained with the specimen under study make it possible to evaluate the age of the source by the ratio of low- and high-energy regions of the spectrum.

The combined detector (CD) comprises a single crystalline plate of ZnSe(Te) placed onto the output window of a scintillating transparent light guide made of CsI(Tl) in the shape of a truncated pyramid. The CsI(Tl) light guide is used to create an additional channel for detection of γ-radiation, as well as for protecting the photodiode from the penetrating radiation. It is shown that introduction of the light guide does not worsen the energy resolution characteristics of ZnSe(Te). Separate detection of - and γ-radiation has been achieved under simultaneous excitation by ²³⁹Pu (ZnSe(Te), R=6%) and ²⁴¹Am (CsI(Tl), R_γ=20%). The use of selective optical filters allows separation of the peaks of total absorption (p.t.a.) in the case of their superposition.     

The CPLEAR electromagnetic calorimeter

A large-acceptance lead/gas sampling electromagnetic calorimeter (ECAL) was constructed for the CPLEAR experiment to detect photons from decays of π⁰s with momentum p_π⁰ ≤ 800 MeV/c. The main purpose of the ECAL is to determine the decay vertex of neutral-kaon decays K⁰ → π⁰π⁰ → 4γ and K⁰ → π⁰π⁰π⁰ → 6γ. This requires a position-sensitive photon detector with high spatial granularity in r−, −, and z−coordinates. The ECAL - a barrel without end-caps located inside a magnetic field of 0.44 T - consists of 18 identical concentric layers. Each layer of 1/3 radiation length (X₀) contains a converter plate followed by small cross-section high-gain tubes of 2640 mm active length which are sandwiched by passive pick-up strip plates. The ECAL, with a total of 6X₀ has an energy resolution of and a position resolution of 4.5 mm for the shower foot. The shower topology allows separation of electrons from pions. The design, construction, read-out electronics, and performance of the detector are described.     

Thermal neutron cross-section and resonance integral for Dy(n,γ)Dy reaction

The thermal neutron cross-section (σ₀) and the resonance integral (I₀) of the reaction ¹⁶⁴Dy(n,γ)¹⁶⁵Dy were measured by the activation method, using ⁵⁵Mn(n,γ)⁵⁵Mn monitor reaction as a single comparator. The diluted MnO₂ and Dy₂O₃ powder samples within and without a cylindrical Cd shield case were irradiated in an isotropic neutron field obtained from the ²⁴¹Am–Be neutron sources, moderated with paraffin wax. The γ-ray spectra from the irradiated samples were measured by high-resolution γ-ray spectrometry with a calibrated n-type Ge detector. The necessary correction factors for γ-ray attenuation, thermal neutron and resonance neutron self-shielding effects and epithermal neutron spectrum shape factor () were taken into account in the determinations. The thermal neutron cross-section for ¹⁶⁴Dy(n,γ)¹⁶⁵Dy reaction studied has been determined to be 2672±104 b at 0.025 eV. This result has been obtained relative to the reference thermal neutron cross-section value of 13.3±0.1 b for the ⁵⁵Mn(n,γ)⁵⁶Mn reaction. For the thermal neutron cross-section, most of the experimental data and evaluated one in ENDF/B-VI, in general, are in good agreement with the present result. The resonance integral has also been measured relative to the reference value of 14.0±0.3 b for the ⁵⁵Mn(n,γ)⁵⁶Mn monitor reaction using a 1/E¹⁺ epithermal neutron spectrum of the ²⁴¹Am–Be neutron source. By defining Cd cut-off energy 0.55 eV, the resonance integral obtained was 527±89 b. The existing experimental and evaluated data for the resonance integral are distributed from 335 to 820 b. The present resonance integral value agrees with some previously reported values, 520 b by Holden, 505 b by Simonits et al. and 575±100 b by Heft, within the limits of error.     

Approximated total and full energy peak intrinsic efficiencies of gamma detectors for measuring systems design

Functions characterizing the performance of gauges based on gamma radiation correlate the design parameters and the variables to be measured. The radiation detector is a major component of the gauge. Analytic expressions for the total and full energy peak efficiencies were derived using the mean chord length in the detector's sensitive volume. The errors associated with this approximation were estimated from the distribution of the chord length. The uncertainties found in the determined total intrinsic efficiency are in the range of a few percent for most practical industrial gauges, and up to about 20% in the worst cases. The approximate values are higher than the experimental or theoretical results. The intrinsic full energy peak efficiency determined by the analytic expression is compared with experimental results for NaI 1″ × 1″ and 3″ × 3″ with ¹³⁷Cs and ⁶⁰Co sources. Results from Monte Carlo calculations agree within 10% with the determination. These errors are acceptable at the design state, as later both source activity and counting time may be adjusted to yield the required statistical uncertainty.     

Comparison of radiation damage in lead tungstate crystals under pion and gamma irradiation

Studies of the radiation hardness of lead tungstate crystals produced by the Bogoroditsk Techno-Chemical Plant in Russia and the Shanghai Institute of Ceramics in China have been carried out at IHEP, Protvino. The crystals were irradiated by a 40 GeV pion beam. After full recovery, the same crystals were irradiated using a ¹³⁷Cs γ-ray source. The dose rate profiles along the crystal length were observed to be quite similar. We compare the effects of the two types of radiation on the crystal's light output.