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.

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Now showing 1 - 5 of 5

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Titanate ceramic matrices for alumina-rich wastes
(Material, 2004) Begg, BD; Vance, ER; Li, HJ; McLeod, TI; Scales, N; Bhati, M
In the early 1980s a synroc variant, SYNROC-D, was developed for immobilisation of high-level defence waste stored at the Savannah River Plant, USA. A key phase in the immobilisation matrix was spinel, used to immobilise the large proportion of iron and alumina in the waste. Here we examine the feasibility of this approach for other alumina-rich wastes, not necessarily containing iron, derived from the dissolution of aluminium fuel cladding. The advantages of using a magnesia spinel, as opposed to hercynite (FeAl2O4), as the primary alumina-bearing phase are discussed in terms of an increase in waste loading and process flexibility. Two options for sodium incorporation, glass and the titanate phase freudenbergite, are considered.
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Synthesis of carboranylphenylalanine for potential use in neutron capture therapy
(Plenum Press, 1993) Prashar, JK; Moore, DE; Wilson, JG; Allen, BJ
The successful use of p-boronophenylalanine (BPA) as the agent for the delivery of boron to melanoma for NCT is based on it being incorporated with tyrosine as a precursor for melanin synthesis. 1 Ideally for the patient undergoing NCT, the boron concentration in the tumour should reach 20 to 30 ppm, and for BPA this level can be achieved by the administration of very high doses. However, the procedure would be improved by a compound with the same affinity for the tumour but with a larger boron content. Consequently a new generation of boronated amino acids are being synthesised to take advantage of the unique bonding characteristics of boron and its ability to form cluster compounds containing up to 12 boron atoms in a compact structure. Following this approach, we have synthesised a 1,2-dicarba-closo-dodecaboranyl derivative of phenylalanine and its nido analogue. © Plenum Press
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Post treatment dose distribution evaluation for a recent NCT patient
(Plenum Press, 1993) Storr, GJ; Wheeler, FJ
As a prelude to establishing, (1) criteria for selection of Boron Neutron Capture Therapy (BNCT) epithermal beam clinical trial patients and (2) treatment planning strategies, post-treatment evaluations of dose distributions in several BNCT patients are being done using the Idaho National Engineering Laboratory (INEL) BNCT Program's patient treatment planning software (bnct-edit and rtt-MC). The objectives of this work are: (i) calculate the dose delivered to the BNCT treated patients (ii) calculate the possible dose distribution for the patients using the proposed Georgia Institute of Technology's reactor epithermal beam (iii) correlate calculated dose with effect © Plenum Press
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A standardized method for beam design in neutron capture therapy
(Plenum Press, 1993) Storr, GJ; Harrington, BV
A desirable end point for a given beam design for Neutron Capture Therapy (NCT) should be quantitative description of tumour control probability and normal tissue damage. Achieving this goal will ultimately rely on data from NCT human clinical trials. Traditional descriptions of beam designs have used a variety of assessment methods to quantify proposed or installed beam designs. These methods include measurement and calculation of open-quotes free fieldclose quotes parameters, such as neutron and gamma flux intensities and energy spectra, and figures-of-merit in tissue equivalent phantoms. The authors propose here a standardized method for beam design in NCT. This method would allow all proposed and existing NCT beam facilities to be compared equally. The traditional approach to determining a quantitative description of tumour control probability and normal tissue damage in NCT research may be described by the following path: Beam design → dosimetry → macroscopic effects → microscopic effects. Methods exist that allow neutron and gamma fluxes and energy dependence to be calculated and measured to good accuracy. By using this information and intermediate dosimetric quantities such as kerma factors for neutrons and gammas, macroscopic effect (absorbed dose) in geometries of tissue or tissue-equivalent materials can be calculated. After this stage, for NCT the data begins to become more sparse and in some areas ambiguous. Uncertainties in the Relative Biological Effectiveness (RBE) of some NCT dose components means that beam designs based on assumptions considered valid a few years ago may have to be reassessed. A standard method is therefore useful for comparing different NCT facilities. © Plenum Press
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Gadolinium as an element for neutron capture therapy
(Plenum Press, 1993) Brugger, RM; Liu, HB; Laster, BH; Gordon, CR; Greenberg, DD; Warkentien, LS
Gadolinium is being studied as an alternate active element to B for Neutron Capture Therapy (NCT). The advantages of Gd-157 as compared to B-10 are that Gd-157 has a very large thermal neutron cross section (455,000 b), and Gd containing compounds that target tumors are being developed as MRI contrast agents. A disadvantage is that the products of the Gd + n reaction, gamma rays and Auger electrons, do not appear to be as well suited to NCT as the products of the B + n reaction, but these still may be effective in destroying tumors. Because of the advantages of Gd, an investigation of Gd as an element for NCT is proceeding at Brookhaven National Laboratory (BNL)1. © Plenum Press