Use of basic principle of nucleation in determining temperature–threshold neutron energy relationship in superheated emulsions

Detection of neutrons through use of superheated emulsions has been known for about two decades. The minimum neutron energy (threshold) required to nucleate drops of a given liquid has a dependence on the temperature of the liquid. The basic principle of nucleation has been utilized to find the relationship between the operating temperature and threshold neutron energy for superheated emulsions made of R-114 liquid. The threshold energy thus determined for different temperatures has been compared with accurate experimental results obtained using monoenergetic neutron sources. The agreement is found to be satisfactory and confirms the applicability of the present simple method to other liquids.     

Radiation detection by using superheated droplets

The superheated emulsion, a radiation detector consisting of superheated droplets dispersed in a gel or a solid matrix, has been in use for some time now. It was initially designed to detect neutrons but also has been modified to detect energetic photons and heavy ions. It has been primarily used as a neutron dosimeter, but has also been used to obtain the energy spectrum for neutrons from Am–Be. The general features of the superheated emulsion detector along with newer analytic methods to obtain more precise results using it as an active device will be presented.     

Threshold temperature for γ-ray detection in superheated drop detector

The γ-ray detection threshold temperatures of superheated drops of refrigerant liquid R-12 is presented here for the three γ-ray energies 59.54 keV (²⁴¹Am, 500 mCi), 662 keV (¹³⁷Cs, 32.5 mCi) and 1250 keV (⁶⁰Co, 0.45 mCi). Nucleation was detected with an active device by counting the number of drops vaporized per minute as a function of the temperature of the detector over a wide range. The results show that the threshold temperature for detection increases with the energy of the incident photons.     

Performance comparison of 2.8 MeV and <Superscript>241</Superscript>Am-Be neutrons based moisture measurement setups

Performance of a ²⁴¹Am-Be neutron source-based and 2.8 MeV neutrons-based moisture measurement setups have been compared using Monte Carlo simulation. In the setup fast neutrons transmitted through the sample were detected by a fast neutron detector, which was placed behind a massive long double truncated collimator. The setup geometry was optimized to detect maximum effect of 1–7 wt.% moisture on the neutron intensity transmitted through the sample. The yield of neutrons transmitted through concrete, coal, wood and soil samples containing 1–7 wt.% moisture was calculated for 2.8 MeV neutrons and neutrons from an ²⁴¹Am-Be source. The slopes of the fast neutron intensities transmitted through the samples vs. their moisture contents are very sensitive to the neutron energy and the sample composition. Higher slopes have been observed for the samples with larger bulk density. The slopes of fast neutron yield show dependence on the incident neutron energy. Larger slopes have been observed for neutrons with samller energy. Due to the overall large slopes of the transmitted intensity data of the samples for 2.8 MeV neutrons, it is expected to achieve better sensitivity in moisture measurements for a 2.8 MeV neutrons based moisture setup.     

The application of selected radionuclides for monitoring of the D–D reactions produced by dense plasma-focus device

The dense plasma focus (DPF) device—DPF-1000U which is operated at the Institute of Plasma Physics and Laser Microfusion is the largest that type plasma experiment in the world. The plasma that is formed in large plasma experiments is characterized by vast numbers of parameters. All of them need to be monitored. A neutron activation method occupies a high position among others plasma diagnostic methods. The above method is off-line, remote, and an integrated one. The plasma which has enough temperature to bring about nuclear fusion reactions is always a strong source of neutrons that leave the reactions area and take along energy and important information on plasma parameters and properties as well. Silver as activated material is used as an effective way of neutrons measurement, especially when they are emitted in the form of short pulses like as it happens from the plasma produced in Dense Plasma-Focus devices. Other elements such as beryllium and yttrium are newly introduced and currently tested at the Institute of Plasma Physics and Laser Microfusion to use them in suitable activation neutron detectors. Some specially designed massive indium samples have been recently adopted for angular neutrons distribution measurements (vertical and horizontal) and have been used in the recent plasma experiment conducted on the DPF-1000U device. This choice was substantiated by relatively long half-lives of the neutron induced isotopes and the threshold character of the ¹¹⁵In(n,n′)^115mIn nuclear reaction.     

A method for bulk hydrogen analysis based on transmission and back scattering of fast neutrons

A method was proposed for bulk hydrogen analysis. It is based on simultaneous detection of transmitted fast neutrons and back scattered thermal neutrons from the investigated samples by ³He detectors. The fast neutron beams were obtained from ²⁵²Cf and Pu–Be neutron sources. The experimental set-up as well as samples preparation were described. Incident thermal neutrons beams obtained from either ²⁵²Cf or Pu–Be sources, were used to investigate the samples by neutron backscattering. The results obtained from transmission and backscattering of fast neutrons were compared and discussed. The advantage and capabilities of the proposed method were presented. The results obtained using fast neutron beams are more sensitive than those obtained using thermal neutron beams. Validation procedures were proposed to credit the results.     

Effective threshold energies for (n, 2n) reactions induced in a fission neutron spectrum

The table presents computed values of effective threshold energies, E_eff, for (n, 2n) reactions induced in a fission neutron spectrum. E_eff-values are given for the (n, 2n) reactions for which the charge of the target nucleus is greater than 11 and for which the reaction product cannot be formed by (n, γ) reaction on another stable isotope. A closed expression is given for the integral of a fission neutron distribution of the Cranberg type, N(E), and for the mean energy of the fission neutrons with spectral distribution N(E).     

Photoneutron spectra around an 18 MV LINAC

Photoneutron spectra around an 18 MV LINAC were calculated in order to observe the effect produced by media around the accelerator. Calculations were carried out with MCNP 4C code, three different cases were analyzed: Head model, Head and phantom model, and Head, air, phantom and wall model. The spectra were calculated in five detectors located at the irradiation room at different distances from the isocentre. A sixth detector, located near the entrance door was included to analyze how the maze change the neutron spectrum. Neutrons are mainly produced in the LINAC head change the shape of evaporation neutrons from the source term, some of these neutrons leak out the head with lesser energy, another neutrons goes with the treatment beam. At any site near the isocentre neutron spectrum has evaporation and thermal neutrons joined by a set of epithermal neutrons. As the distance from the isocentre increases evaporation neutrons tend to decrease while, epithermal and thermal neutrons tend to remain constant regardless de distance due to room return produced by the walls. The maze contributes to reduce the neutron fluence, reducing the evaporation neutrons; resulting spectrum is mainly the contribution of thermal and epithermal neutrons. Near the door these neutrons can produce activation and prompt gamma rays.     

Determination of fluorine in geological samples using accelerator derived neutrons

A fast, neutron activation analysis technique is described for the determination of fluorine in geological samples. The method utilises the reaction¹⁹F(n,α)¹⁶N for the determination. However, it avoids the interference reaction from oxygen which produces the same radionuclide since the neutrons are derived from the bombardment of beryllium with 3 MeV deuterons. The maximum energy of the neutrons so produced is well below the threshold for the competing oxygen reaction. The results indicate that the method gives acceptable accuracy over the range of a few tens ppm to several percent fluorine content using suitable standards. Sample analysis time is only a few minutes allowing the analyses of large numbers of samples per day.     

A review of intercomparison exercises run by NPL from 1989–1997

The flux of cold neutrons that is obtainable from various high energy netron sources is studied for a particular model of a cold neutron source when the cold moderation region of the apparatus is at 20, 70, and 298K. The maximum flux obtained with a californium-252 source was 2.7·10^?3 cold neutron per (cm²·second (source neutron)). This flux was obtained when the cold moderation region of the apparatus was at 20K and when the thermal moderator is either polyethylene or trimethylbenzene and the cold moderator is polyethylene. This flux should allow sensitive prompt and delayed neutron activation analysis measurements.     

First experimental attempts of129I direct measurements by neutron interrogation and gamma-ray spectrometry

As an altemative to¹²⁹I measurement by X-ray spectrometry or ICPMS, we explored the possibilities of activation analysis using thermal or 14 MeV neutrons. Preliminary qualitative measurements were done with samples of about 5 mg. These samples were exposed to two neutron sources:²⁵²Cf and DT neutron generator. The most interesting reaction is the neutron capture which leads to useful signatures at 536.1, 668.5, and 739.5 keV, associated with a half-life of 12.36 h.     

Development of a Bonner sphere spectrometer with emphasis on decreasing the contribution of scattering by using a new designed shadow cone

In this study, the Bonner sphere spectrometer (BSS) used for measurement of neutron spectra based a BF₃ long counter. The most important problem for this system was a high count of scattered neutrons. This spectrometer was established by designed a new shadow cone with a smaller length and improved attenuation coefficient. Because of shortening the length of the shadow cone, distance of source and center of the sphere was decreased. Furthermore, external part of the thermal detector was covered with a suitable layer to reduce the contribution count of scattering neutrons. Experimental results show that BSS system with BF₃ long cylindrical counter, applying the proper developments, can be used in neutron fluence spectrometry.     

Further Development of a Novel Neutron Detector Using the Single Event Upset Phenomenon in Dynamic Random Access Memories

The potential of using a commercially available 1 Mbit dRAM as a neutron detector within an improved neutron area monitor has been studied. The response of three manufacturers 1 Mbit dRAMs to low energy alpha particles from ¹⁴⁸Gd has been determined. Their use as a thermal neutron detector, by the application of a charged particle converter to the die surface, was also examined. Whilst it was demonstrated that they responded to low energy alpha particles their sensitivity to neutrons was found to be too low for them to be used within a neutron area monitor.     

Time and depth dependent fluxes due to 14 MeV neutrons impinging soil

A spectroscopy system measuring inelastic neutron scattering and thermal neutron capture induced gamma-rays is being developed for in-situ soil analysis. Because a pulsed fast D-T neutron source is utilized, fast neutron induced inelastic neutron scattering reactions are separated in time from thermal neutron capture events. Models utilizing the MCNPX code have been developed to study the time and energy variations of the neutrons in the soil matrix.     

On the use of bismuth as a neutron filter

A formula is given which, for neutron energies in the range 10⁻⁴<E<10 eV, permits calculation of the nuclear capture, thermal diffuse and Bragg scattering cross-sections as a function of bismuth temperature and crystalline form. Computer programs have been developed which allow calculations for the Bi rhombohedral structure in its poly-crystalline form and its equivalent hexagonal close-packed structure. The calculated total neutron cross-sections for poly-crystalline Bi at different temperatures were compared with the measured values. An overall agreement is indicated between the formula fits and experimental data. Agreement was also obtained for values of Bi-single crystals, at room and liquid nitrogen temperatures. A feasibility study for use of Bi in powdered form, as a cold neutron filter, is detailed in terms of the optimum Bi-single crystal thickness, mosaic spread, temperature and cutting plane for efficient transmission of thermal-reactor neutrons, and also for rejection of the accompanying fast neutrons and gamma rays.     

A response-function approach to the direct calculation of the transition-energy in a multiple-cluster expansion formalism

Approximate limiting collision induced dissociation (CID) probabilities are calculated as a function of the vibrational energy and temperature for HCl, HF and O₂, infinitely diluted in an inert gas, by assuming that only the molecules with an energy that is within kT below the threshold dissociate and do so with unit probability. Rotational energy is explicitly included in defining the threshold for dissociation. At the lowest temperatures of our calculations (2500 K for HCl and HF, 3500 K for O₂) the agreement between the calculated CID probabilities and those obtained by us earlier in fitting the experimental dissociation rates is quite remarkable for HCl and HF and satisfactory for O₂ at all vibrational energies. It is therefore argued that the ladder climbing model and the weak bias model for diatomic dissociation are not different in principle if rotational energy is properly accounted for.     

Prompt-gamma neutron activation analysis system design: Effects of D-T versus D-D neutron generator source selection

Prompt-gamma neutron activation (PGNA) analysis is used for the non-invasive measurement of human body composition. Advancements in portable, compact neutron generator design have made those devices attractive as neutron sources. Two distinct generators are available: D-D with 2.5 MeV and D-T with 14.2 MeV neutrons. To compare the performance of these two units in our present PGNA system, we performed Monte Carlo simulations (MCNP-5; Los Alamos National Laboratory) evaluating the nitrogen reactions produced in tissue-equivalent phantoms and the effects of background interference on the gamma-detectors. Monte Carlo response curves showed increased gamma production per unit dose when using the D-D generator, suggesting that it is the more suitable choice for smaller sized subjects. The increased penetration by higher energy neutrons produced by the D-T generator supports its utility when examining larger, especially obese, subjects. A clinical PGNA analysis design incorporating both neutron generator options may be the best choice for a system required to measure a wide range of subject phenotypes.     

Fast neutron activation analysis at Texas A&M University

Fast neutron generators are used at Texas A & M University to provide a supply of high energy neutrons for nuclear analytical measurements. A series of neutron activation analysis procedures have been developed for determining various major, minor and trace constituents in a variety of materials. These procedures are primarily developed to compliment our reactor based NAA program, thereby expanding the list of determinable elements to include those difficult or impossible to measure using thermal neutrons. A few typical methods are discussed. The unique implementation of the methodologies at Texas A & M are explained.     

Photoneutrons from a beryllium reflector: a potential source of problems with Zr–Au flux monitors in <Emphasis Type="Italic">k</Emphasis><Subscript>0</Subscript> standardization based neutron activation analysis

The assumption that the shape of the epithermal neutron spectrum can be described, in any research reactor, by the 1/E ^1+α function is a fundamental starting point of the k ₀ standardization. This assumption may be questioned from a reactor physics viewpoint. The type of moderator, the existence of neutron reflectors, the additional production of (γ, n) neutrons and resonance capture by construction materials may be different for each reactor, with consequences for the shape of the neutron spectrum. This dependency may explain that various practitioners reported contradicting experiences with the use of Zr–Au flux monitors for the determination of the α-parameter. An objective view on the influence of the design of the reactor and irradiation facility on the shape of the neutron spectrum can be obtained by modeling. This has been applied in the Reactor Institute Delft for reactor configurations in which the irradiation facilities face the fuel elements with the presence of beryllium reflector elements. The Monte Carlo calculations indicate a distortion of the 1/E ^1+α relationship at the higher energy edge of the epithermal neutron spectrum. This distortion is attributed to the formation and thermalisation of both photoneutrons and (n, 2n) produced fast neutrons in the beryllium, and has a direct impact on the resonance activation of ⁹⁵Zr, other than represented by the 1/E ^1+α function. The obtained relationship between neutron flux and neutron energy was also used for estimating the f-value and compared with the value obtained by the Delft Cr–Mo–Au flux monitor.     

Activation analysis by means of resonance neutrons and polarized particles

The fundamentals of neutron reasonance analysis (NRA) are briefly discussed, and results demonstrating increased selectivity obtained by means of NRA are presented. Three variations of NRA are described, namely activation, absorption and spectral resonance methods of the slowing down time of neutrons based on the absorption and time selection of neutrons with defined energies. The potentialities of utilizing polarized neutrons for elemental analysis are discussed.