There is strong evidence that water-ice is relatively abundant within permanently shadowed lunar surface materials, particularly at the poles. Evidence for water-ice has been observed within the impact plume of the LCROSS mission and is supported by data gathered from the Lunar Exploration Neutron Detector (LEND) and the Lunar Prospector Neutron Spectrometer (LPNS). Albedo neutrons from the Moon are used for detection of hydrogen, where the epi-thermal neutron flux decreases as hydrogen content increases. The origin on the concentration of water within permanently shadowed regions is not completely understood, and the Lunar Polar Hydrogen Mapper (LunaH-Map) mission is designed to provide a high-resolution spatial distribution of the hydrogen content over the southern pole using a highly elliptical, low perilune orbit. The LunaH-Map spacecraft is a 6U cubesat consisting of the Miniature Neutron Spectrometer (Mini-NS). Mini-NS is not collimated, requiring a low altitude to achieve a higher spatial resolution compared to previous missions. To develop a compact neutron detector for epi-thermal neutrons, the Mini-NS comprises of 2-cm thick slabs of CLYC (Cs2LiYCl6), which provide a sensitivity similar to a 10-atm, 5.7-cm diameter He-3 tubes, as used in LPNS. The Mini-NS digital processing electronics can discriminate by shape and height to determine signal (albedo neutrons) from background (cosmic rays). The Mini-NS achieves a total active sensing area of 200 cm(2) and is covered with a cadmium sheet to shield against thermal neutrons. The research and development on the detector modules show a robust design ready for space flight.

A novel broad spectrum neutron spectrometer has been created to extend the useful energy range of existing neutron Bonner Sphere Spectrometers (BSS). Both an active LiI(Eu) scintillator probe and passive gold foil detector were utilized to extend the energy response of the existing BSS. Above 20 MeV the energy structure for the standard polyethylene BSS are poor because the response functions are not unique. MCNPX was used to investigate several modifications to the BSS system which resulted in the Bonner Sphere Extension (BSE). This cost effective extension uses several concentric spheres of copper, lead, and tungsten heavy metal downscatter materials to extend the useful range of the current BSS from 20 MeV to above 1 GeV. Using both a 3" and 5" inner polyethylene spheres, aluminum shell sets were made with a 1" cavity and filled with the high Z materials for six total sets of spheres. a 12" and 8" polyethylene sphere were also milled to accept the heavy metal spheres. The system was validated at the Los Alamos Neutron Science Center (LANSCE) neutron beam. The system was calibrated at LANSCE for neutrons up to 800 MeV on target 4's 15 degree right flightpath (4FP15R) at 90 meters. Detailed models in MCNPX were made of the BSS, BSE and LANSCE facilities. Fine group responses were made and compared to the unfolded data from LANSCE. A vast improvement over the BSS system alone was seen with reasonable agreement with time of flight data measured at LANSCE and MCNPX calculated neutron spectra.

The work focuses on Monte Carlo simulations for finding the optimal back scatter time-of-flight spectrometer design for concept testing at the NESSA facility at Uppsala University. The spectrometer consists of two scintillator detectors, D1 (placed in a neutron beam) and D2 (placed in front of D1), at some distance from each other. A fraction of the neutrons that impinge on D1 back scatter into D2 and information on the neutron energy distribution is acquired using the time-of-flight method. For the given constraints on geometry, resolution and efficiency a best resolution was found to be 6.6% with a corresponding efficiency of 1E-4 which gives a sufficient count rate for a neutron generator producing 1E+11 neutrons/s. In order to achieve a minimum of 10 000 counts/h with the same setup a D2 with an area of at least 7 cm^2 is required.

En France, les références associées à la fluence neutronique et aux grandeurs dosimétriques dérivées sont détenues par le Laboratoire de Métrologie, de micro-irradiation et de Dosimétrie des Neutrons (LMDN) de l’IRSN. Afin d’améliorer la définition des références en énergie et en fluence des champs neutroniques monoénergétiques de l’installation AMANDE,le LMDN s’est engagé dans le projet de développement d’un détecteur gazeux μTPC (microTime Projection Chamber) appelé LNE-IRSN-MIMAC en collaboration avec le LPSC.Dans une précédente thèse, la mesure de champs neutroniques entre 27 keV et 565 keV a été réalisée. L’objectif de ce travail de thèse est d’étendre la gamme de mesure au-delà de 1 MeV.Le choix du gaz, le développement d’une méthode d’analyse indépendante de l’utilisateur et la caractérisation du détecteur ont ainsi permis de valider la capacité du détecteur LNE-IRSN-MIMAC à réaliser des mesures dans des champs neutroniques monoénergétiques entre 250 keV et 6,5 MeV avec une précision de 3% en énergie et de 2,5% en fluence. / In France, the references associated to the neutron fluence and the deriva-ted dosimetric quantities are under the responsability of the micro-irradiation and neutronmetrology and dosimetry laboratory (LMDN)of IRSN. In order to improve the definition ofreferences in fluence and energy of the monoenergetic neutron fields, produced at AMANDEfacility, a micro-TPC gaseous detector, called LNE-IRSN-MIMAC, is developping in collabo-ration with LPSC.In a previous work, the detector was qualified for neutron fields in the energy rangebetween 27 keV and 565 keV. The objective of the present work is to extend the range of theμTPC above 1 MeV. The choice of the gas, the development of an analysis method and thedetector characterization allowed to validate the detector capacity to perform measurements inmonoenergetic neutron fields ranging from 250 keV up to 6,5 MeV with a relative uncertaintyof 3% and 2,5% respectively in energy and fluence.

The neutron plays a central role in numerous fields of physics, a fact that entails a need for methods of measuring neutron energy spectra. In this project, a technique for neutron spectrometry through measurements of neutron-induced radioactivity in activation detectors was developed and tested. The developed technique involves irradiating element samples with neutrons, measuring activation products with a gamma spectrometer, and then performing a neutron spectrum unfolding procedure. The elements indium, iron, magnesium, aluminium, zinc, titanium, and copper were used as activation detectors and irradiated with neutrons from an americium-beryllium (AmBe) neutron source. Subsequent gamma spectrometry was performed with the UGGLA high-purity germanium detector setup at Uppsala University. The GRAVEL unfolding algorithm was implemented in MATLAB and used to unfold neutron spectra based on an initial spectrum guess. The unfolded neutron spectrum agrees well with the expected AmBe spectrum, though some difference between the spectra is attributed to neutron scattering in the irradiation environment. A possible ability to find approximate neutron spectra from inaccurate initial guesses is found, but additional work is needed to understand better how the initial guess affects the result for different neutron sources. Because activation detectors do not require electrical power when measuring neutrons, can be made sensitive to a wide range of neutron energies, and do not detect other types of radiation, future applications could find the developed neutron spectrometry method practical.

科学研究費補助金 研究種目:一般研究(C) 課題番号:04680228 研究代表者:青山 隆彦 研究期間:1992-1993年度