Numerical simulation on scintillator detector response for determining element content in PGNAA system

For selecting gamma ray detector to determining element content using prompt gamma neutron activation analysis technique, the response of BGO and LaBr₃ scintillator detectors was compared with Monte Carlo simulation method. The simulation models under different formation composed of various elements were established by MCNP, and then gamma ray spectrum was processed by least squares method. It is concluded that the element calculation accuracy will be different when scintillator was changed. With higher energy resolution, LaBr₃ scintillator can be used to improve the accuracy of the element content calculation result, and is more suitable for plentiful element formation.

     

Self-calibration method for cerium-doped lanthanum bromide scintillator detector in the 0.1–2.0 MeV energy range

In recent years, the cerium-doped lanthanum bromide, LaBr₃ (Ce = 5 %) detector is increasingly playing an important role in radiation measurements because of its higher energy resolution (~3 % at 662 keV), faster luminescence decay time (~35 ns) and higher detection efficiency compared to 7.65 cm × 7.65 cm NaI(Tl) detector. Intrinsic spectra between 1,800 and 3,000 keV derived from internal radioactivity within LaBr₃(Ce) scintillators have been investigated in some literatures, and these results are confirmed by the experiments in this work. In this paper, a new method for LaBr₃(Ce) detector energy calibration from 100 to 2,000 keV is proposed using the intrinsic spectra (self-calibration) instead of the standard gamma sources. Proof-of-concept experiment results show that self-calibration can guarantee energy accuracy of better than 0.815 % and can be applied outside the laboratory. The stability and applicability of this method are also investigated systematically.     

Experimental comparison of the relative yield of 3γ/2γ positron annihilation using semiconductor and scintillation detectors

The yield of three photon positron annihilation is measured using semiconductor and scintillation detectors in a comparison for applications in positron emission tomography, particularly in the exploitation of three photon positron annihilation imaging where good energy resolution and good efficiency are required. In this experimental study four detectors, High-purity Germanium (HPGe), Sodium Iodide (NaI(Tl)), Lanthanum Chloride (LaCl₃:10%Ce³⁺) and Lanthanum Bromide (LaBr₃:5%Ce³⁺) were used. The peak-to-peak method was used with a ²²Na source to determine these yields. Aluminium was employed as a reference material as its high electron density reduces positronium formation and lifetimes. Teflon was also used in order to enhance the formation of ortho-positronium, since quenching is low, leading to increased three photon positron annihilation. The relative 3γ/2γ yields obtained were (3.04±0.11)·10⁻², (2.17±0.11)·10⁻², (3.26±0.10)·10⁻² and (2.03±0.11)·10⁻² for LaBr₃:Ce, LaCl₃:Ce, NaI(Tl) and HPGe detectors, respectively. Among these detectors LaBr₃:Ce proved to be the detector of choice for three photon imaging applications as it has both good energy resolution and efficiency.     

Characterization of LaBr<Subscript>3</Subscript>: Ce and LaCl<Subscript>3</Subscript>: Ce scintillators for gamma-ray spectroscopy

This study aims to investigate the performance of relatively new cerium-doped scintillators, LaCl₃ and LaBr₃, for gamma-ray spectroscopy. The study involved recording of detected spectra and measurement of energy resolution, as well as photo-fraction. The Monte Carlo package, GATE, was used to validate the experiments. In general, the energy resolution figures achieved were twice as good as that of NaI(Tl). In conclusion, LaBr₃: Ce and LaCl₃: Ce crystals have excellent energy resolution, (2.13±0.03)% and (2.92±0.04)% at 1332 keV, respectively, and comparable photo-fraction to NaI(Tl). Hence, these crystals, particularly LaBr₃: Ce, have the potential to replace NaI(Tl) as the scintillator of choice for γ-ray spectroscopy.     

Comparison of portable detectors for uranium enrichment measurements

Uranium enrichment and holdup measurements require a detector capable of accurately obtaining the 186-keV peak area. NaI detectors have been widely used for these tasks. However, for recycled uranium, the interference of the 239-keV peak from the ²³²U decay chain challenges the capabilities of the NaI detectors to accurately extract the area of the 186-keV peak. Using CZT detectors, which have much better resolution than the NaI detectors, has temporarily solved this interference problem. However, the CZT detectors have setbacks in that they are generally small and have low efficiencies, which require long acquisition times for reasonable statistics. Recently, two new types of scintillator detectors have become available commercially, LaCl₃(Ce) and LaBr₃(Ce). These cerium-doped lanthanum halide detectors, with comparable resolution but better efficiency than the CZT detectors, appear to permanently solve the interference problem for recycled uranium measurements. In this report, we compare the uranium enrichment measurement performances of a portable NaI detector, a large coplanar-grid CZT detector, and a LaBr₃ detector.     

Application of the multiple isotope material basis set (MIMBS) method of isotope identification to low energy gamma emitters

The multiple isotope material basis set (MIMBS) method for isotope identification combines the material basis set (MBS) model of gamma spectrum attenuation with ordinary response function fitting to identify shielded gamma-emitting isotopes, using low and medium resolution gamma detectors such as NaI and LaBr₃. Although MIMBS has been shown to outperform conventional isotope identification algorithms that do not correct for attenuation effects, it has difficulty identifying low energy emitters such as ⁵⁷Co or ²⁴¹Am. In this article we examine the use of optimized multiple attenuator thicknesses in generating basis spectra for each isotope to obtain better modeling of the low energy spectrum while simultaneously extending the range of the model to thicker attenuators. The effectiveness of the multiple thickness MIMBS algorithm in improving isotope identification rates compared with the original MIMBS method is demonstrated with analyses of simulated gamma spectra. The identification rates obtained with the MIMBS methods are compared to those obtained using the commercial peak-based ScintiVision NaI analysis software.     

Enthalpy of Phase Transitions and Heat Capacity of Stoichiometric Compounds in LaBr3-MBr Systems (M=K,Rb, Cs)

Molar enthalpies of solid-solid and solid-liquid phase transitions of the LaBr₃, K₂LaBr₅, Rb₂LaBr₅, Rb₃LaBr₆ and Cs₃LaBr₆ compounds were determined by differential scanning calorimetry. K₂LaBr₅ and Rb₂LaBr₅ exist at ambient temperature and melt congruently at 875 and 864 K, respectively, with corresponding enthalpies of 81.5 and 77.2 kJ mol^-1. Rb₃LaBr₆ and Cs₃LaBr₆ are the only 3:1 compounds existing in the investigated systems. The first one forms from RbBr and Rb₂LaBr₅ at 700 K with an enthalpy of 44.0 kJ mol^-1 and melts congruently at 940 K with an enthalpy of 46.7 kJ mol^-1. The second one exists at room temperature, undergoes a solid-solid phase transition at 725 K with an enthalpy of 9.0 kJ mol^-1 and melts congruently at 1013 K with an enthalpy of 57.6 kJ mol^-1. Two other compounds existing in the CsBr-based systems (Cs₂LaBr₅ and CsLa₂Br₇) decompose peritectically at 765 and 828 K, respectively. The heat capacities of the above compounds in the solid as well as in the liquid phase were determined by differential scanning calorimetry. A special method - 'step method' developed by SETARAM was applied in these measurements. The heat capacity experimental data were fitted by a polynomial temperature dependence. This revised version was published online in July 2006 with corrections to the Cover Date.     

Determination of depth of a radionuclide source in a tissue equivalent phantom

Hydrophilic materials which refer to a group of cross-linked polymers originally developed in the 60s to produce soft contact lenses are characterised by an equilibrium water uptake in the range 15–95 % by wet weight when hydrated in water or normal saline solution at 25 °C. This ability to absorb controlled amounts of water makes them suitable human tissue substitutes. Four types of hydrophilic materials of different composition and thickness were placed between a ²²Na calibrated point source and a single LaBr₃: Ce (5 %) detector (Saint-Gobain) at a fixed distance between source and detector. The scatter-to-peak ratio was determined by selecting five scatter angle windows between 25 and 50^° (467–376 keV), at 5^° intervals, to study how the ratio varied with attenuating material, thickness and composition. From photon spectra recorded a ‘best’ estimate of the depth of the source in the hydrophilic material was obtained by finding the most sensitive scattering window. Theoretical and practical models of the source-to-detector geometries are included and discussed.     

稀土掺杂Lu3Al5O12荧光粉的发光特性及能量传递

采用高温固相法制备了Ce、Sm共掺Lu_3Al_5O_(12)荧光粉。通过X射线衍射分析、荧光光谱分析研究了样品的结构、发光特性,并通过理论计算研究了能量传递效率、能量传递的临界距离以及能量传递方式。X射线衍射分析表明所制备的荧光粉具有单一的石榴石结构;荧光光谱分析表明,在464 nm蓝光激发下,Sm~(3+)的引入可增加Lu_3Al_5O_(12)∶Ce,Sm发射光谱中红光成分,并且随着Sm~(3+)浓度的增加,Ce~(3+)发光强度逐渐减弱。计算出Ce~(3+)、Sm~(3+)之间的能量传递效率高达77.42%,确定了Ce~(3+)、Sm~(3+)之间的能量传递机制为偶极-偶极相互作用。     

Evaluation of an alternative convenient irradiation system for determination of emission rate of radio-isotopic neutron sources

In present work, an alternative irradiation system based on a symmetric cylindrical tank filled with a moderator containing hydrogen, which was equipped with a NaI(Tl) scintillation detector, was proposed for using in determination of neutron flux. This irradiation system was designed by MCNP4C code, with considering a ²⁴¹Am–Be neutron source in several volumes and different materials. When the neutron is captured by hydrogen, a 2.22 MeV prompt gamma-ray is emitted. The gamma pulse-height spectrum shows a photo-peak around 2.22 MeV whose net area is proportional to the total emission rate of neutron. The simulation result showed that a cylindrical tank with 110 cm diameter and height filled with water can be a suitable system for neutron source strength calibration. Furthermore, a proper two-layer shielding must be placed between the source and detector for preventing neutrons and gamma rays to directly enter the detector.     

Monte Carlo simulation of Cu,Ni and Fe grade determination in borehole by PGNAA technique

A prompt gamma neutron activation analysis borehole logging method for copper, nickel and iron grade estimation is proposed. The performance of the method was simulated by MCNP5 code. Based on the theory of neutron–gamma distribution on the borehole condition, the BGO scintillator and ³He neutron tube are adopted to record gamma ray spectrum and thermal neutron simultaneously, and least square method is used for the characteristic gamma ray counts calculation in the high energy range. The results of detection limit of metal grade in borehole condition indicate that the effectiveness of this logging method.     

Chemical characterization of graphite by instrumental neutron activation analysis

Nuclear and commercial grade graphite samples were analysed by instrumental neutron activation analysis (INAA) using high flux reactor neutrons. Eleven elements (Na, K, As, Sc, Fe, Cr, Co, Zn, La, Ce, and Sm) were determined in eight samples of graphite (two nuclear grade and six commercial grade) by irradiating at a neutron flux of 3?×?10¹³ cm^?2 s^?1 in CIRUS reactor and assaying the activity by high-resolution gamma ray spectrometry using 40% relative efficiency HPGe detector coupled to an MCA. Concentrations of elements were determined by relative method of INAA. Results of both types of graphites as well as detection limits achieved by INAA method are discussed in the paper.     

Bismuth radionuclides in the natural background gamma radiation spectrum

The natural background gamma (NBG) spectrum was accumulated inside the laboratory, with 102.88 cm³ Ge(Li) detector, to investigate bismuth natural radionuclides in the energy range of 500–1700 keV. The relative intensities of identified²¹⁴Bi gamma lines were obtained from the spectrum. The results were in good agreement with that obtained from a source of a precise strength. Out of the 25 gamma lines of²¹⁴Bi, 19 lines were established including 6 lines observed for the first time in the NBG spectrum. Most of the gamma lines of²¹¹Bi and²¹²Bi were observed. Some of these lines are new.     

Verbindungen der Seltenerdelemente mit α-Benzoinoxim, 1. Mitt.

Zusammenfassung Substanzen der ZusammensetzungLnCl₃·3H₂ Box ^* (Ln=La, Ce, Pr, Nd, Sm, Eu, Gd, Tb, Dy, Ho, Er, Y) und LaBr₃·3 H₂ Box wurden isoliert und durch Thermoanalyse, IR-Absorptionsspektren und Röntgenstreuung charakterisiert.

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Compounds of the rare earth elements with -benzoin oxime

Compounds of compositionLnCl₃·3 H₂ Box ^* (Ln=La, Ce, Pr, Nd, Sm, Eu, Gd, Tb, Dy, Ho, Er, Y) and LaBr₃·3H₂ Box were isolated and characterized by thermoanalysis, IR spectroscopy and X-ray diffraction.

     

BaHfO3：Ce粉体活化能对烧结透光性影响

用正、反向共沉淀法制备了BaHfO₃：Ce粒子;用XRD、TG-DTA、SEM等测试手段对样品的物相、形貌及发光性能进行了表征;在不同升温速率条件下研究了粒子合成动力学。结果表明：由正向和反向沉淀法得到的前驱体物相变化分3个阶段,用Doyle-Ozawa和Kissinger法分别计算了各阶段的表观活化能,其平均值分别为83.41、61.70、262.11kJ·mol^-1和81.70、42.86、253.44kJ·mol^-1,计算正反向沉淀法样品的晶粒生长活化能分别为27.36kJ·mol^-1和23.07kJ·mol^-1;反向法的样品分别在530nm波长下的激发光谱和399nm波长的发射光谱的相对发光强度优于正向法,在2073K真空烧结保温3h获得具有一定透光性的BaHfO₃：Ce透明陶瓷。     

BaHfO_3∶Ce粉体活化能对烧结透光性影响

用正、反向共沉淀法制备了BaHfO3∶Ce粒子;用XRD、TG-DTA、SEM等测试手段对样品的物相、形貌及发光性能进行了表征;在不同升温速率条件下研究了粒子合成动力学。结果表明:由正向和反向沉淀法得到的前驱体物相变化分3个阶段,用Doyle-Ozawa和Kissinger法分别计算了各阶段的表观活化能,其平均值分别为83.41、61.70、262.11 kJ·mol-1和81.70、42.86、253.44 kJ·mol-1,计算正反向沉淀法样品的晶粒生长活化能分别为27.36 kJ·mol-1和23.07 kJ·mol-1;反向法的样品分别在530nm波长下的激发光谱和399 nm波长的发射光谱的相对发光强度优于正向法,在2 073 K真空烧结保温3 h获得具有一定透光性的BaHfO3∶Ce透明陶瓷。     

Measurement of three gamma annihilation by lanthanum-based crystals compared with NaI(Tl) and HPGe

The relative yield of 3γ to 2γ annihilation was measured for a positron emitter, ²²Na, with the new scintillator detectors lanthanum chloride (LaCl₃:Ce) and lanthanum bromide (LaBr₃:Ce), which had been characterised for comparison with high-purity germanium (HPGe) and sodium iodide (NaI(Tl)) detectors. The information obtained from the ortho-positronium 3γ decay in positron emission tomography (PET) can be a measure of the oxygen content in biological tissues by determination of this relative yield. However, it requires high resolution spectroscopy and detection efficiency. Characterisation of the new generation of scintillator detectors determines whether they could replace conventional scintillators and semiconductors. A series of experiments was carried out with different samples in order to study the effect of ortho-positronium formation. The peak-to-peak and the peak-to-valley methods were compared in the measurement of the relative yield of 3γ to 2γ annihilation.     

Neutron/gamma discrimination in LiBaF3 scintillator

The detection of neutrons in the presence of significant gamma-radiation is often required in arms control, material accountability, and nuclear smuggling scenarios as well as in basic nuclear research. The new scintillator material LiBaF₃ offers the possibility of measuring neutron count rates and energy spectra simultaneously while measuring gamma-count rates and spectra using a single detector. These capabilities derive from the fact that LiBaF₃ exhibits a very fast core-valence luminescence under gamma-irradiation whereas this component is missing under neutron irradiation. Relatively simple pulse shape analysis techniques can be used to obtain excellent neutron/gamma discrimination. We present our current results illustrating these capabilities.     

Application of fast solvent extraction processes to studies of exotic nuclides

The nucleus²³Na has been investigated by studying the primary γ-rays emitted from 53 keV neutron capture in it using a high resolution and high efficiency (100%) HPGe detector and NaI(T1) detector for anti-Compton. 24 primary γ-rays were placed in the²⁴Na, in which 3 primary γ-rays were new ones from a (n, γ) reaction, and reported for the first time. In order to obtain an exact energy calibration within 7 MeV,⁵⁶Fe(n,γ)⁵⁷Fe reaction was used at thermal neutron energy. Intensity calibration was obtained from the²⁷Al(p,γ)²⁸Si reaction atE _p=2046 keV. The neutron binding energy of²⁴Na was determined to be 6959.75 keV.     

Neutron energy spectra of 252Cf, Am-Be source and of the D(d,n)3He reaction

The neutron energy spectrum of the following sources were measured using a fast neutron spectrometer with the NE-213 liquid scintillator: ²⁵²Cf, Am-Be and D(d,n)³He reaction from a 3 MeV Pelletron accelerator in Tokyo Institute of Technology. The measured proton recoil pulse height data of ²⁵²Cf, Am-Be and D(d,n)³He were unfolded using the mathematical program to obtain the neutron energy spectrum. The ²⁵²Cf and Am-Be neutron energy spectra were measured and the results obtained showed a good agreement with the spectra usually published in the literature. The neutron energy spectrum from D(d,n)³He was measured and the results obtained also showed a good agreement with the calculation by time of flight (TOF) methods.