Polonium-210 and Lead-210 activities measured on 9 water bottle profiles during POLARSTERN cruise ANT-XXIV/3

As part of the GEOTRACES Polarstern expedition ANT XXIV/3 (ZERO and DRAKE), Polonium-210 and Lead-210 have been measured in the water column and on suspended particulate matter in February to April 2008. Our goal was to resolve the affinities of 210Po and 210Pb to transparent exopolymer particles (TEP) and particulate organic carbon (POC). Polonium-210 and Lead-210 in the ocean can be used to identify the sources and sinks of suspended matter. In seawater, Polonium-210 (210Po) and Lead-210 (210Pb) are produced by stepwise radioactive decay of Uranium-238. 210Po (138 days half life) and 210Pb (22.3 years half life) have high affinities for suspended particles. Those radionuclides are present in dissolved form and adsorbed onto particles. Following adsorption onto particle surfaces, 210Po especially is transported into the interior of cells where it bonds to proteins. In this way, 210Po also accumulates in the food chain. 210Po is therefore considered to be a good tracer for POC, and traces particle export over a timescale of months. 210Pb (22.3 years half life) adsorbs preferably onto structural components of cells, biogenic silica and lithogenic particles, and is therefore a better tracer more rapidly sinking matter. Water samples were taken with Niskin bottles. Dissolved Polonium-210 and Lead-210 activities refer to the fraction < 1µm. Particulate Polonium-210 and Lead-210 refer to the activity on particles >1µm retained on nucleopore filters. Zooplankton retained on the filters was systematically removed as this study focused on phytoplankton and exudates. The data have been submitted to Pangaea following a Polonium-Lead intercalibration exercise organized by GEOTRACES, where the AWI lab results range within the data standard deviation from 10 participating labs.

Social movements and the crisis of neoliberalism in Malaysia and Thailand

Of the Southeast Asian countries most badly affected by the 1997 financial crisis, Malaysia and Thailand remain the most unsettled by its political fallout. Their present political situations are not akin to 'politics as usual'. Instead, they capture the unpredicted outcomes of post-crisis struggles to reorganize structures of economic and political power. Comparing the situations in Malaysia and Thailand, this paper focuses on their differing state and civil society engagements with neoliberalism. It is suggested that the post-crisis contestations, sometimes tied to pre-crisis conflicts in political economy, left something of a stalemate: neither neoliberalism nor the social movements satisfactorily fulfilled their agendas in either country.

Propagation of Nuclear Data Uncertainties in Transmutation Calculations Using ACAB Code

The assessment of the accuracy of parameters related to the reactor core performance (e.g., ke) and f el cycle (e.g., isotopic evolution/transmutation) due to the uncertainties in the basic nuclear data (ND) is a critical issue. Different error propagation techniques (adjoint/forward sensitivity analysis procedures and/or Monte Carlo technique) can be used to address by computational simulation the systematic propagation of uncertainties on the final parameters. To perform this uncertainty assessment, the ENDF covariance les (variance/correlation in energy and cross- reactions-isotopes correlations) are required. In this paper, we assess the impact of ND uncertainties on the isotopic prediction for a conceptual design of a modular European Facility for Industrial Transmutation (EFIT) for a discharge burnup of 150 GWd/tHM. The complete set of uncertainty data for cross sections (EAF2007/UN, SCALE6.0/COVA-44G), radioactive decay and fission yield data (JEFF-3.1.1) are processed and used in ACAB code.

Uncertainty methods inactivation and inventory calculations

For a number of important nuclides, complete activation data libraries with covariance data will be produced, so that uncertainty propagation in fuel cycle codes (in this case ACAB,FISPIN, ...) can be developed and tested. Eventually, fuel inventory codes should be able to handle the complete set of uncertainty data, i.e. those of nuclear reactions (cross sections, etc.), radioactive decay and fission yield data. For this, capabilities will be developed both to produce covariance data and to propagate the uncertainties through the inventory calculations.