ANSTO Publications Online

Welcome to the ANSTO Institutional Repository known as APO.

The APO database has been migrated to version 7.5. The functionality has changed, but the content remains the same.

ANSTO Publications Online is a digital repository for publications authored by ANSTO staff since 2007. The Repository also contains ANSTO Publications, such as Reports and Promotional Material. ANSTO publications prior to 2007 continue to be added progressively as they are in identified in the library. ANSTO authors can be identified under a single point of entry within the database. The citation is as it appears on the item, even with incorrect spelling, which is marked by (sic) or with additional notes in the description field.

If items are only held in hardcopy in the ANSTO Library collection notes are being added to the item to identify the Dewey Call number: as DDC followed by the number.

APO will be integrated with the Research Information System which is currently being implemented at ANSTO. The flow on effect will be permission to publish, which should allow pre-prints and post prints to be added where content is locked behind a paywall. To determine which version can be added to APO authors should check Sherpa Romeo. ANSTO research is increasingly being published in open access due mainly to the Council of Australian University Librarians read and publish agreements, and some direct publisher agreements with our organisation. In addition, open access items are also facilitated through collaboration and open access agreements with overseas authors such as Plan S.

ANSTO authors are encouraged to use a CC-BY licence when publishing open access. Statistics have been returned to the database and are now visible to users to show item usage and where this usage is coming from.

Contact the Repository

 

Communities in ANSTO Publications Online

Select a community to browse its collections.

Now showing 1 - 5 of 5

Recent Submissions

No Thumbnail Available
Item
Radiation doses via inhalation and ingestion under the current and proposed ICRP models
(AINSE, 1989-09-22) Twining, JR
The ICRP are considering lowering the limits for radiation exposure by at least a factor of two. In the Australian sand-mining industry the implications of this decision are that exposure limits will probably be exceeded if the current models for dose estimation are retained. In fact, the current limits are proving difficult to achieve due to the nature of the separation processes involving monazite. If default AMAD values are used and respiration protection factors are not applied using the current model some workers could be considered to be over-exposed. However, as part of the process of redefinition, the ICRP task group on lung dynamics will also be presenting a revised inhalation exposure model which will appear fairly soon after the new recommendations are released. The biological bases for the new model are discussed as is the likely influence the new lung model will have on dose assessment via inhalation and ingestion, which are the critical pathways in the sand-mining industry. The current and proposed models are described and the performance of the models is compared for class Y materials in which thorium (the main radiotoxic constituent of monazite) is included. Doses to lymph and bone from translocated inhaled material are considered with reference to clinical data, as are the dose implications of material translocated to the gastrointestinal tract from the lungs or from direct ingestion. The general effect of the new model is such that by using more realistic deposition and clearance factors the committed effective dose equivalents are reduced by a factor of 5-10 thereby more than compensating for the expected reduction in ICRP exposure limits when applied with the current lung model.
No Thumbnail Available
Item
The ANSTO body protein monitor
(AINSE, 1991-10-02) Blagojevic, N; Allen, BJ
The first Body Protein Monitor (BPM) to operate in Australia was fabricated at the Lucas Heights Research Laboratories in 1985. In collaboration with The Children's Hospital, Camperdown, this instrument was successfully used in a study of protein deposition in children with cystic fibrosis. Other clinical studies followed of end-stage renal failure and the effects of aortic surgery. Current projects include phenylketonuria, anorexia nervosa, liver disease and transplantation, synthetic growth hormone, intravenous fat emulsions, and paediatric arthritis. Some six Sydney hospitals are involved with these projects. The ANSTO prototype ANSTO BPM is now located in the Nuclear Medicine Department of the Royal North Shore Hospital. The widespread application of the BPM and its acceptance by Sydney medical specialists as a vital element in clinical trials led to the design and fabrication of a commercial model. This unit has been sold to the University of Texas Medical Branch, and has been designed to study obese subjects. The BPM features a computer controlled table operation which allows all subjects to be measured to the same statistical precision. The Am Be neutron sources, supplied by the customer, can be turned on and off by virtue of rotating shield and collimator drums. Other features include the low background around the monitor, aluminium construction, top and bottom neutron sources, 4 high efficiency 10 x 10 x 20cm Nal detectors and the 7 minute counting time. There is also a provision for a bismuth germanate detector for the direct measurement of whole body chlorine. The IBM PC computer system is based on the Canberra S100 multichannel analysis card and Microsoft Windows Software operation.
No Thumbnail Available
Item
Neutron capture therapy with Gadolinium-157
(1989) Allen, BJ; McGregor, BJ; Martin, RF
The nuclear characteristics of the boron-IO neutron capture reaction that make it so suitable for neutron capture therapy are the high capture cross-section (3838 barns), the high linear energy transfer (LET > 100 keV/um) and short range (6 — 10 um) of the reaction products [8]. If the boron-IO atom is taken up by the cancer cell, on average 2.33 MeV of high LET radiation is deposited within the cell per capture event, causing double strand breaks (dsb) in the DNA and mitotic impotence. There are other neutron capture reactions with larger cross-sections but these produce gamma-rays and have been considered to be of little importance to radiotherapy. However these reaction invariably lead to internal conversion and subsequent emission of Auger electrons. Experiments with 1251 have demonstrated that dsb can be induced upon decay of 1251 that is either covalently incorporated into DNA [10] or noncovalently associated with DNA [11]. Monte Carlo studies of 1251 decay by electron capture or internal conversion indicate that in the condensed phase 21 Auger electrons are emitted per decay with total energy of 19.8 kev [2]. The range of the majority of these electrons is of molecular dimensions and the ionisation density exceeds that of a 5 MeV alpha particle [1]. Further, charge effects caused by the generation of electrons may well be the major cause of damage [4]. Thus critical damage to DNA can result from highly localised, microscopic stochastic patterns of energy deposition. Internal conversion also occurs following neutron capture in 157Gd [7], and because this isotope has a neutron capture cross-section 67 times larger than 10B it was of interest to see whether DNA dsbs could be induced by neutron capture of DNA bound 157Gd. neutron capture event, and the electron holes so created in the K and L shells are filled by Auger and Coster-Kronig transitions, with the concomitant emission of low energy electrons with very short range. In a recent experiment at the Moata reactor [9], we were able to demonstrate that Auger electron emission from neutron capture in 157Gd was able to induce double strand breaks in plasmid DNA. It is therefore of interest to calculate the neutron-gamma-ray transport in tissue to evaluate the effect of the 7.937 MeV binding energy released in the capture reaction. © 1989Urbun &Vogel GMBH
No Thumbnail Available
Item
Morphological changes in melanoma cells following irradiation
(AINSE, 1989-09-22) Barkla, DH; Allen, BJ; Brown, JK; Buck, S
Three lines of melanoma cells (two human, one murine) were propagated in tissue culture flasks and then subjected to either gamma irradiation (using a 60Co, source) or thermal neutron irradiation (in the MOATA reactor). Some flasks were treated with 10 boronophenylalanine (BPA) prior to neutron irradiation to simulate neutron capture therapy (NCT) . Flasks of cells were then fixed at 24 hr intervals over the next 20 days and prepared for examination using light microscopy and transmission electron microscopy. Other flasks of cells were analysed for melanin content before and after irradiation. During days 1-5 after irradiation many cells detached from the floor of the flasks and died. Changes in cell morphology after irradiation were similar for gamma-treated and 10B +ve and 10B -ve NCT-treated cells. Early changes seen during days 1-3 included abnormalities in both the plasma membrane and the nuclear membrane of melanoma cells, changes presumably leading to cell death. During days 6-12, surviving cells showed evidence of differentiation into subpopulations of cells showing increased melanin content . During days 13-20, these changes continued and, in addition, flasks were gradually repopulated with cells having a morphology similar to that of the pre-irradiated cells . The apparent increase in melanin content after irradiation was confirmed statistically using a melanin assay. The results suggest that gamma and thermal neutron irradiation operate similarly, and disrupt the integrity of both nuclear and plasma membranes. The relationship between these changes and damage to DNA is unclear. Morphological changes distinctive of the neutron capture reaction of thermal neutrons by 10BPA were not apparent. © The Author.
Thumbnail Image
Item
The relative importance of radioecological parameters in tropical and subtropical regions - the use of a radiological consequence model to focus research
(Institute for Environmental Sciences, Japan, 1997-10-16) Harris, FF; Domel, RU; Crawford, J
The scientific understanding of radioecological parameters within tropical and subtropical regions is relatively poor and many parameters are either unknown or have very large uncertainties. A research program has been initiated to investigate these data deficiencies and commence targeted research into the parameters with the most significant effect on the radiological consequences following releases of radioactivity for critical groups in the South East Asian region. A computer based model has been developed to assess the radiological consequences and to determine the most significant parameters for the region. The radiological consequence model includes a user-friendly graphical interface and is designed to investigate the dose effects of various scenarios, radioecological parameters, pathways and critical groups. The ability to perform sensitivity and uncertainty analysis on the data will allow the most significant radioecological parameters to be determined. Initially, the model will deal with the South East Asian region but flexibility has been incorporated into the design to allow application in other regions. The importance of local foodstuffs, soil conditions, climatic considerations, agricultural practices and critical group diets has been emphasised by this preliminary work. Variations in both critical radionuclides and pathways are important when tropical and subtropical transfer parameters, diets and lifestyles are considered.