[en] Following a brief description of the reactor some of the history of ZED-2 will be described, particularly in so far as it relates to the development of reactor physics methods used in the design and analysis of CANDU power reactors.

[en] An electron (or positron) multi-bunch train traversing several thousand accelerator structures can be distorted by the long-range wakefields left behind accelerated bunches. These wakefields can at the very least, give rise to a dilution in the emittance of the beam and, at worst can lead to a beam break up instability. The authors investigate the emittance dilution that occurs for various frequency errors (corresponding to small errors made in the design or fabrication of the structure) for the GLC/NLC (Global Linear Collider/Next Linear Collider) and for TESLA (TeV Energy Superconducting Linear Accelerator). Resonant effects, which can be particularly damaging, are studied for X-band and L-band linacs

[en] The X-band linacs for the G/NLC (Global/Next Linear Collider) have evolved from the DDS (Damped Detuned Structure) series. The present accelerating structures are 60 cm in length and incorporate damping and detuning of the dipole modes which comprise the wakefield. In order to adequately damp the wakefield, frequencies of adjacent structures are interleaved. Limited analysis has been done previously on the higher order dipole bands. Here, we calculate the contribution of higher order bands of interleaved structures to the wakefield. Beam dynamics issues are also studied

[en] The next generation of linear colliders will consist of several tens of thousands of accelerating structures and this will entail inevitable errors in the dimensions and alignments of cells and groups thereof. These errors result in a dilution of the beam emittance and consequently a loss in overall luminosity of the collider. For this reason it is important to understand the alignment tolerances and frequency tolerances that are imposed for a specified emittance budget. Here we specify an emittance dilution of no more than 10% of the injected nominal value of 20 nm.rads and we track the progress of the beam down the linac whilst accelerating structures (and sub-sections thereof) are misaligned in a random manner. Random frequencies are also incorporated in the misalignment analyses. Tolerances are specified for both frequency errors and misalignment errors

[en] The United States (U.S.) currently utilizes a once-through fuel cycle where used nuclear fuel (UNF) is stored on-site in either wet pools or in dry storage systems with ultimate disposal in a deep mined geologic repository envisioned. This strategy of minimal fuel handling generates only small quantities of low level waste. Within the Department of Energy's (DOE) Office of Nuclear Energy (DOE-NE), the Fuel Cycle Technology (FCT) Program develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development of advanced fuel cycles, including modified open and closed cycles. These advanced cycles, requiring some level of handling and rework of used fuel, inherently have the potential to increase low level waste generation - in some cases substantially. This study analyzes the quantities of various low level waste streams as a function of a variety of potential fuel cycle alternatives including: (1) Geologic disposal of commercial UNF generated by uranium fuel light water reactors (LWR); (2) Four alternative LWR used fuel recycling processes that differ in the reprocessing method (aqueous vs. electro-chemical), complexity (Pu only or full transuranic (TRU) recovery) and waste forms generated; and (3) Reprocessing of fuels derived from recovered TRU utilizing multiple reactor passes.

[en] Several of the prospective salt disposition alternative technologies require a monosodium titanate (MST) contact to remove strontium and actinides from inorganic salt solution feedstock. This feedstock also contains sludge solids from waste removal operations and may contain defoamers added in the evaporator systems. Filtration is required to remove the sludge and MST solids before sending the salt solution for further processing. This report describes testing performed using the Parallel Theological Experimental Filter (PREF). The PREF contains two single tube Mott sintered metal crossflow filters. For this test one filter was isolated so that the maximum velocities could be achieved. Previous studies showed slurries of MST and sludge in the presence of sodium tetraphenylborate (NaTPB) were filterable since the NaTPB slurry formed a filter cake which aided in removing the smaller MST and sludge particles. Some of the salt disposition alternative technologies do not use NaTPB raising the question of how effective crossflow filtration is with a feed stream containing only sludge and MST. Variables investigated included axial velocity, transmembrane pressure, defoamer effects, and solids concentration (MST and sludge). Details of the tests are outlined in the technical report WSRC-RP-98-O0691. Key conclusions from this study are: (1) Severe fouling of the Mott sintered metal filter did not occur with any of the solutions filtered. (2) The highest fluxes, in the range of .46 to 1.02 gpm/f², were obtained when salt solution decanted from settled solids was fed to the filter. These fluxes would achieve 92 to 204 gpm filtrate production for the current ITP filters. The filtrate fluxes were close to the flux of 0.42 gpm/f² reported for In Tank Precipitation Salt Solution by Morrisey. (3) For the range of solids loading studied, the filter flux ranged from .04 to .17 gpm/f² which would result in a filtrate production rate of 9 to 31 gpm for the current HP filter. (4) Filtrate flux for slurries containing solids and defoamers was between the range of .04 to .13 gpm/f² which is better than the average flux of 0.024 gpm/f² reported for Late Wash. (5) Filtrate flux is weakly dependent on the variables of insoluble solids concentration, defoamer concentration, transmembrane pressure, axial velocity, and filtration time

[en] The ZED-2 Reactor at Chalk River Laboratories was 50 years old this fall. First criticality occurred in September 1960. ZED-2 is perhaps not very well known in the Canadian Nuclear Industry, certainly not as well known as the various CANDU power reactors or the research reactors NRU and NRX. Part of the reason for this I suspect is that when casually judging the importance of reactors the first parameters that spring to mind are power generated (for power reactors) or neutron flux (for research reactors), bigger being 'better in both cases. By these standards ZED-2 does indeed appear puny: the maximum allowed power is 200W and the corresponding flux about 10⁸ to 10⁹ neutrons cm^-2 s^-1, both numbers being about a factor of 500,000 smaller than the corresponding values for NRU. So, what is it all about? How is it that such an apparently insignificant reactor has operated for 50 years?, longer than any other Canadian reactor except NRU and the McMaster Reactor. What is it used for? What contributions has it made to the Canadian industry? Maybe one might also ask for how long is it going to continue? Well, that's what this talk is about, although I think I will leave the final question to wiser heads than mine. ZED-2 is a descendant of famous progenitors: starting with Enrico Farm's first critical pile of graphite and uranium (created at the University of Chicago in 1942) through Canada's ZEEP (first reactor to go critical outside the USA) that went critical in 1945. These early critical facilities were first about proof of principle that a self sustaining nuclear chain reaction could be established and controlled in a reasonable sized facility and second, in the longer term, developing understanding of the underlying reactor physics and the development of theories and methods to accurately predict the important properties of critical assemblies generally. (author)

[en] This paper is a parameter study which examines a wide range of circular, elliptical, and 'D' shaped equilibria and finds a convenient parameter for categorizing their properties. The author assumes that interchange instabilities are stabilized by the average mininum β property, while stabilisation of axisymmetric perturbations and kinks is provided by wall feedback. Since the theory of localized or 'balooning' MHD modes is still controversial, the author restricts most of the discussions to equilibrium criteria

[en] A multi-bunch beam, traversing travelling wave accelerator structures, each with a 5π/6 phase advance per cell, is accelerated at a frequency that is synchronous with the fundamental mode frequency. As per design, the main interaction occurs at the working frequency of 11.424 GHz. However, modes with frequencies surrounding the dominant accelerating mode are also excited and these give rise to additional modal components to the wakefield. Here, we consider the additional modes in the context of X-band accelerator structures for the GLC/NLC (Global Linear Collider/Next Linear Collider). Finite element simulations and field mode-matching models are employed in order to calculate the wakefield

[en] Each of the X-band accelerating structures for the GLC/NLC (Global Linear Collider/Next Linear Collider) consists of 55 cells which accelerate a train of charged bunches. The cells are carefully designed to ensure that the transverse wakefield left behind each bunch does not disrupt the trailing bunches, but some modes are trapped in the region of the coupler cells. These modes can give rise to severe emittance dilution if care is not taken to avoid a region of resonant growth in the emittance. Here, we present results on simulations, cold test experimental measurements and beam dynamics simulations arising as a consequence of modes trapped in the coupler. The region in which trapped modes have little influence on the beam is delineated