David C Glasgow

Research Activities on Neutrorics under ASTE Collaboration at AGS/BNL

A series of experiments on a mercury spallation target using high-peak-power GeV proton-beam from the Alternating Gradient Synchrotron (AGS) of Brookhaven National Laboratory (BNL) has been performed under an international collaboration among the laboratories in Japan, U.S. and Europe, namely the ASTE (AGS Spallation Target Experiment) collaboration. This paper reviews the current status of the experiments on neutronic performance of the mercury target.

Analysis of a neutronic experiment on a simulated mercury spallation neutron target assembly bombarded by giga-electron-volt protons

Abstract A neutronic benchmark experiment on a simulated spallation neutron target assembly was conducted by using the Alternating Gradient Synchrotron at Brookhaven National Laboratory and was analyzed to investigate the prediction capability of Monte Carlo simulation codes used in neutronic designs of spallation neutron sources. The target assembly consisting of a mercury target, a light water moderator, and a lead reflector was bombarded by 1.94-, 12-, and 24-GeV protons, and the fast neutron flux distributions around the target and the spectra of thermal neutrons leaking from the moderator were measured in the experiment. In this study, the Monte Carlo particle transport simulation codes NMTC/JAM, MCNPX, and MCNP-4A with associated cross-section data in JENDL and LA-150 were verified based on benchmark analysis of the experiment. As a result, all the calculations predicted the measured quantities adequately; calculated integral fluxes of fast and thermal neutrons agreed approximately within ±40% with the experiments although the overall energy range encompassed more than 12 orders of magnitude. Accordingly, it was concluded that these simulation codes and cross-section data were adequate for neutronics designs of spallation neutron sources.

Methods for preparing comparative standards and field samples for neutron activation analysis of soil

One of the more difficult problems associated with comparative neutron activation analysis (CNAA) is the preparation of standards which are tailor-made to the desired irradiation and counting conditions. Frequently, there simply is not a suitable standard available commercially, or the resulting gamma spectrum is convoluted with interferences. In a recent soil analysis project, the need arose for standards which contained about 35 elements. In response, a computer spreadsheet was developed to calculate the appropriate amount of each element so that the resulting gamma spectrum is relatively free of interferences. Incorporated in the program are options for calculating all of the irradiation and counting parameters including activity produced, necessary flux/bombardment time, counting time, and appropriate source-to-detector distance. The result is multi-element standards for CNAA which have optimal concentrations. The program retains ease of use without sacrificing capability. In addition to optimized standard production, a novel soil homogenization technique was developed which is a low cost, highly efficient alternative to commercially available homogenization systems. Comparative neutron activation analysis for large scale projects has been made easier through these advancements. This paper contains details of the design and function of the NAA spreadsheet and innovative sample handling techniques.

The simultaneous determination of 235U and 239Pu using delayed neutron activation analysis

Delayed neutron activation analysis (DNAA) remains one of the most sensitive methods of nondestructively determining fissile materials in a variety of sample matrices, provided that the samples contain only a single fissile component. This has historically been the limiting factor in many applications of DNAA, and often chemically destructive methods of analysis have needed to be utilized for many real-world samples. This work seeks to develop a method that will allow for DNAA to be utilized on samples containing multiple fissile components. Initial efforts, presented here, show that using a multivariate linear regression model to describe the delayed neutron emission profile of an irradiated sample allows for the concurrent determination of fissile nuclides in samples containing both 235U and 239Pu, without chemical separations and using only a single counting step.

Proton Induced Activation in Mercury: Comparison of Measurements and Calculations

Measurements and simulations of the proton beam interaction with the mercury target were performed to support Spallation Neutron Source design. Due to the abundance of isotopes produced in mercury, the long delay between the irradiation and the measurements, and the self-shielding of the mercury sample, the measurements were difficult to perform and the activities of several isotopes have large uncertainties. Calculations predicted the activities of the most reliably measured isotopes within 20%–40%; however, some large discrepancies were observed for some isotopes for which the measurements were considered less reliable. Predicted dose rates were in very good agreement with the measurements.

Novel technique for ultra-sensitive determination of trace elements in organic scintillators

A technique based on neutron activation has been developed for an extremely high sensitivity analysis of trace elements in organic materials. Organic materials are sealed in plastic or high purity quartz and irradiated at the HFIR and MITR. The most volatile materials such as liquid scintillator (LS) are first preconcentrated by clean vacuum evaporation. Activities of interest are separated from side activities by acid digestion and ion exchange. The technique has been applied to study the liquid scintillator used in the KamLAND neutrino experiment. Detection limits of <2.4×10 15 g 40 K/g LS, <5.5×10 15 g Th/g LS, and <8×10 15 g U/g LS have been achieved.

SLEEPING REACTOR IRRADIATIONS : THE USE OF A SHUT-DOWN REACTOR FOR THE DETERMINATION OF ELEMENTS WITH SHORT-LIVED ACTIVATION PRODUCTS

Neutron activation analysis utilizing the High Flux Isotope Reactor (HFIR) immediately following SCRAM is a workable solution to obtaining data for ultra-short lived species, principally Al, Ti, Mg, and V. Neutrons are produced in the HFIR core within the beryllium reflector due to gamma-ray bombardment from the spent fuel element. This neutron flux is not constant, varying by over two orders of magnitude during the first 24 hours. The problems associated with irradiation in a changing neutron flux are removed through the use of a specially tailored activation equation. This activation equation is applicable to any irradiation at HFIR in the first 24 hours after SCRAM since the fuel elements are identical from cycle to cycle, and the gamma-emitting nuclides responsible for the neutrons reach saturation during the fuel cycle. Reference material tests demonstrate that this method is successful, and detection limit estimates reveal that it should be applicable to materials of widely ranging mass and composition.

Foil analysis of 1.5-GeV proton bombardment of a mercury target

Abstract The number of reactant nuclei in a series of foils surrounding a container of mercury that has been bombarded by 1.5-GeV protons is calculated and compared with experimental measurements. This procedure is done to aid in the validation of the mercury cross sections used in the design studies of the Spallation Neutron Source (SNS). It is found that the calculations match the measurements to within the uncertainties inherent in the analysis.

Neutron activation by neutrons produced via proton-induced spallation in a liquid-mercury target: Measurements and assessment of uncertainties

A preliminary test of a liquid mercury target for the production of neutrons by spallation was undertaken at the Alternating Gradient Synchrotron facility at Brookhaven National Laboratory. Neutron activation of elemental foils placed on the target demonstrates that a range of neutron energies does exist, as expected, and that the neutron flux is at a maximum 10–20 cm from the front of the target, moving deeper with increasing proton energy. Uncertainties in the activity calculations are in general significantly <10%. Impurities in some of the foils are a significant source of interference for some reactions, although there is no interference for most of the reactions. The presence of many interference-free reactions, along with the low uncertainties indicates that the foils will be useful benchmarks to validate the neutronics codes utilized in the target design.

Radioactive foil analysis of 1.5 GeV proton bombardment of a Hg target

The number of reactant nuclei in a series of foils surrounding a container of Hg that has been bombarded by 1.5 GeV protons is calculated and compared to experimental measurements. This is done to aid in the validation of the Hg cross sections used in the design studies of the Spallation Neutron Source (SNS). It was found that the calculations match the measurements to within the uncertainties inherent in the analysis.