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ANSTO Publications Online

Welcome to the ANSTO Institutional Repository known as APO.

The APO database has been migrated to version 8.3. 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

Recent Submissions

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    ChemInform Abstract: Antiferromagnetism in a technetium oxide. Structure of CaTcO3
    (Wiley, 2011-04-14) Avdeev, M; Thorogood, GJ; Carter, ML; Kennedy, BJ; Ting, J; Singh, DJ; Wallwork, KS
    Abstract The title compound is prepared by solid state reaction of NH 4 TcO 4 and Ca(NO 3 ) 2 (flowing Ar, 700 °C, 1 h). © Wiley
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    Advantages hot isostatically pressed ceramic and glass-ceramic waste forms bring to the immobilization of challenging intermediate- and high-level nuclear wastes
    (Trans Tech Publications, 2011-01-05) Vance, ER; Moricca, SA; Begg, BD; Stewart, MWA; Zhang, YJ; Carter, ML
    Hot isostatic pressing (HIP) is a technology with wide applicability in consolidating calcined intermediate-level and high-level nuclear waste, especially with wastes that are not able to be readily processed by vitrification at reasonable waste loadings. The essential process steps during the HIP cycle will be outlined. We have demonstrated the effective consolidation via HIP technology of a wide variety of tailored glass-ceramic and ceramic waste forms, notably simulated ICPP waste calcines, I sorbed upon zeolite beads, Pu-bearing wastes, inactive Cs/Sr/Rb/Ba mixtures, simulated waste pyroprocessing salts from spent nuclear fuel recycling, Tc, U-rich isotope production waste, and simulated K-basin (Hanford, WA, USA) and Magnox sludges (UK). Can-ceramic interactions have been carefully studied. The principal advantages of the HIP technology include: negligible offgas during the high temperature consolidation step, relatively small footprint, and high waste loadings. As a batch process, the wasteform chemistry can be readily adjusted on a given process line, to deliver wastes into different end states (e.g. direct HIP versus chemically tailored). This flexibility allows the treatment of multiple waste streams on the one process line. © 2011 Trans Tech Publications Ltd.
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    Progress in the development of LEU fuel
    (American Nuclear Society, 2007-12-01) Wachs, DM; Keiser, DD; Meyer, M; Burkes, D; Clark, C; Moore, G; Jue, JF; Finlay, MR; Totev, T; Hofman, GL; Wiencek, T; Kim, YS; Snelgrove, J
    New nuclear fuels are being developed to enable many of the most important research and test reactors worldwide to convert from high enriched uranium (HEU) fuels to low enriched uranium (LEU) fuels without significant loss in performance. The development work is an international effort lead by the US RERTR program under the NNSA's GTRI. Initial testing (circa 2003) demonstrated that the unexpected tendency of U-Mo fuels dispersed in aluminum toward unstable swelling (pillowing) under high-power conditions. Technical investigations were initiated worldwide at this time by the partners (including Argentina, Canada, France, South Korea and Russia) understand this behaviour as well as to develop and test remedies. This paper gives an overview of the current status of U-Mo fuel development, including basic research results, manufacturing aspects, and the results of the latest irradiations and post irradiation examinations. © American Nuclear Society
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    Recent measurements of neutron capture cross sections in the fission product mass region
    (OECD Nuclear Energy Agency, 1978) Musgrove, ARD; Allen, BJ; Boldeman, JW
    The radiative capture cross sections for the separated isotopes of Sr, Y, Zr, Mo, Pd, Cd, Ba, La, Ce, Pr and Nd in the energy range 3-200 keV were measured with high energy resolution at the 40 m station of the Oak Ridge Electron Linear Accelerator. Maxwellian average 30 keV cross sections and average resonance parameters derived from the analysis are tabulated. A strong dependence of the average radiative widths on neutron binding energy is noted. This leads to a pronounced even-odd disparity. Neutron strength functions reduce with decreasing binding energy along an isotopic owing chain to the decreasing density of doorway state at the binding energy.
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    The fission neutron spectrum from the spontaneous fission of 252Cf
    (OECD Nuclear Energy Agency, 1978) Boldeman, JW; Culley, D; Cawley, RJ
    The fission neutron spectrum from the spontaneous fission of 252Cf has been measured using the time-of-flight method for the energy range 0.6 to 15 MeV. The spectrum was found to be very close to a Maxwellian distribution. In the region 1 to 6 MeV, deviations are less than 2%. Above 8.5 MeV, there is a significant but very small positive deviation from the Maxwellian shape which reaches approximately 15% between 10 and 14 MeV. The value found for the average energy of the Maxwellian is 2.110+-0.020 MeV.