05/00110 Three-particle clusters and the cold-fusion problem Novakovic, L. International Journal o['Hydrogen Energy, 2004, 29, (13), 1397 1407. This study demonstrated, by starting from rather general assumptions, that a cold-fusion research programme can be established on three physically independent approaches; one classical, another quantum- mechanical, and yet another electrodynamical. Equations of motion will be applied to a specific geometric-structural model of three- particle clusters, elp(d)e2 . Here the heavy particle (proton, deuteron) is assumed to perform an orbital motion about the axis which joins the motionless (or almost motionless) el,e2 electrons. Furthermore, this study was towards metallic lattices of the palladium group to see just how the heavy particle can experience such an acrobatic dynamics. For this reason the action of a time-dependent electric field combined with a constant magnetic induction (known as a Lorentz Jbrce) was considered, presumably materialized within a palladium lattice struc- ture, to see a possible physical mechanism by which a particular three- particle cluster may pass from one stationary state to the other.

05•00111 Training of the position controller in SST-1 using TSC simulations Bandyopadhyay, I. et al. Fusion Engineering and Design, 2004, 70, (3), 209-220. For sustenance of the long duration discharges in the Steady State Tokamak (SST-1), it would be necessary to accurately measure and control the plasma shape, radial and vertical positions. While the plasma shape and position would be controlled by a set of super- conducting coils placed outside the vessel and copper feedback control coils placed inside the vessel, their diagnostics would be carried out by an array of magnetic probes placed inside the vessel, just outside the first wall. The main objective of this paper is to demonstrate the reconstruction of plasma position and shape parameters from magnetic probe measurements in steady-state operation. Function parametriza- tion method would be employed to infer the plasma position and shape parameters from the probe signals, which needs large volume of prior database for the probe signals for various plasma positions and shape parameters. This has been generated through SST-1 discharge simulations using the Tokamak Simulation Code (TSC), which generally has excellent agreements with experimental data. The discharge simulations using TSC over a wide range of SST-I plasma parameters and use of the corresponding database in fitting of plasma position and shape parameters to probe signals are presented. It is also shown that the subsequent reconstruction of plasma position and shape from test data also generated from TSC simulations is well within the error limits.

05/00112 Validation study of the cell code WIMS-D and a 69 group library based on JENDL-3,2 Rahman, M. et al. Annals o f Nuelear Energy, 2004, 31, (12), 1357 1383. A new 69-group library of multigroup constants for the lattice code WIMS-D/4 has been generated, processing nuclear data from JENDL- 3.2 using NJOY91.108. A parallel ENDF/B-VI based library has also been constructed for inter-comparison of results. Benchmark calcu- lations for a number of thermal reactor critical assemblies having both uranium and plutonium fuels have been performed with the code WIMS-D/4.1 with three different libraries: the 1986 WIMS library (NEA-0329/10) and the new JENDL-3.2 and ENDF/B-VI based libraries. The benchmark parameters calculated with the two new libraries show similar tendencies and are found in better agreement with the experimental values compared to those with the 1986 WIMS library. Benchmark parameters are further calculated with the comprehensive lattice code SRAC95. The results from WIMS-D/4.1 and SRAC95 agree well with each other as well as to the other previously published values except for lattices with higher plutonium contents. The disagreement is well resolved by an improved resonance treatment and ended up with a clear indication that the 1986 WIMS library with 13-resonance groups is not at all reliable for analysis of mixed oxide (MOX) cores of varying plutonium contents and for burn- up calculation of uranium-fuelled cores.

Economics, policy, supplies, forecasts

05100113 Building the US National Fusion Grid: results from the National Fusion Collaboratory Project Schissel, D. P. et al. Fusion Engineering and Design, 2004, 71, (1-4), 245 250. The US National Fusion Collaboratory Project is developing a persistent infrastructure to enable scientific collaboration for all aspects of magnetic fusion research. The project is creating a robust, user-friendly collaborative software environment and making it

05 Nuclear fuels (economics, policy, supplies, forecasts)

available to more than 1000 fusion scientists in 40 institutions who perform magnetic fusion research in the United States. In particular, the project is developing and deploying a national Fusion Energy Sciences Grid (FusionGrid) that is a system for secure sharing of computation, visualization, and data resources over the Internet. The FusionGrid goal is to allow scientists at remote sites to fully participate in experimental and computational activities as if they were working at a common site thereby creating a virtual organization of the US fusion community. The project is funded by the USDOE Office of Science, Scientific Discovery through Advanced Computing (SciDAC) Program and unites fusion and computer science researchers to directly address these challenges.

05100114 Description and performance of Bulgarian Emergency Response System in case of nuclear accident (BERS) Syrakov, D. et al. International Journal of Environment and Pollution, 2003, 20, (I-6), 286 296. A PC-oriented Emergency Response System in case of nuclear accident (BERS) is developed and works operationally in the National Institute of Meteorology and Hydrology (NIMH) with the Bulgarian Academy of Sciences. The creation and development of BERS was highly stimulated by the ETEX (European Tracer Experiment) project, followed by the European RTMOD (Real-Time Modelling) project. BERS comprises two main parts - the operational and the accidental one, which are applied both to region 'Europe' and the region 'Northern Hemisphere' (versions E and NH). The operational part runs automatically. It makes search for the necessary meteorological data received in NIMH via the Global Telecommunication System (GTS) of the World Meteorological Organization (WMO), prepares the input meteorological file used by both trajectory and dispersion models, creates archives with meteorological data base, runs the trajectory models, visualizes the results obtained and uploads the maps of trajectories for specified nuclear power plants (NPP) to the web site of NIMH. The operational part runs every 12 hours, after the new meteorological information is received. The accidental part is activated manually when a real radioactive releases in the environment occur or during emergency exercises. Two Bulgarian dispersion models - LED and EMAP - are the cores of the accidental part. The concentration and accumulated deposition fields are output by these models. After visualization the concentration and deposition maps are uploaded to the ftp-server of NIMH for use by the interested institutions. In the paper, the BERS overall structure is described and a number of applications are shown including several runs in the frame of the European 5th Framework Programme Project ENSEMBLE.

05/00115 Developments to supplant CAMAC with industry standard technology at NSTX Sichta, P. et al. Fusion Engineering and Design, 2004, 71, (1 4), 129-133. The National Spherical Torus Experiment (NSTX), like other research programmes, is facing an inevitable crisis due to end-of-life issues for its 20-year-old CAMAC (Computer Automated Measurement And Control) instrumentation. In many cases, replacement components are not available, effectively rendering a CAMAC module unusable after a failure. The proliferation of high performance, reliable, low-cost commodity computing hardware and software based on industry standard technology can provide the basis for a new generation of instrumentation. At NSTX, there have been several advances towards developing a PCI-based model for data acquisition and control systems. New hardware developments include a high performance signal conditioning board and a field programmable gate array (FPGA)-based multifunction timing system (MTS). Extensible soft- ware interfaces have been developed to integrate these boards into the NSTX computing environment. This paper will illustrate these developments and how they could be used to benefit collaborative fusion research.

05/00116 Evaluation of the national nuclear energy R&D projects in Korea: multi-attribute utility analysis Kwak, S.-J. et al. International Journal of Global Energy Issues, 2003, 20, (2), 119-138. The Korean government has selected nuclear energy as the major source of electricity generation in Korea because of the lack of domestic energy resources. Thus, nuclear energy has become an increasingly vital part of resources for national development. The national nuclear energy R&D projects have been implemented for ensuring a safe and stable supply of nuclear energy in Korea since 1992. Evaluation of the national nuclear energy R&D projects has critical importance in the aspect of nuclear energy management. This paper employs multi-attribute utility analysis as a basis for obtaining an index to evaluate the national nuclear energy R&D projects using a specific case study of Korea. To structure and quantify basic values for the evaluation, important attributes are determined, then refined and structured into a hierarchy. A multi-attribute index was constructed as

Fuel and Energy Abstracts January 2005 17