First measurement of the BSB_S meson mass

If simplified, every information retrieval problem can be solved when the information need implied by its expression has been identified. We are interested in the criteria used in realising a good information retrieval problem expression. We have listed these criteria through some principles and maxims which first characterized the communication between two persons are applied. We choose to use the gricean maxims because they are the most favoured for this type of situation. Secondly, we have tried to identify some others principles that can be used to realise a good information retrieval problem expression. The principles by Grice can not resolve all forms of error associated with this particular form of communication. In our work, we defined three other principles namely: adhesion principle, reformulation principle, memorization principle. We give some examples of situations where the principles we have formulated are not applicable and the consequences. We present the possible applications of our new model: MIRABEL, which can help in the description of information retrieval problem from. It also compels its user to use essential good expression principle implicitly

Final results from the PERUSE study of first-line pertuzumab plus trastuzumab plus a taxane for HER2-positive locally recurrent or metastatic breast cancer, with a multivariable approach to guide prognostication

Background: The phase III CLinical Evaluation Of Pertuzumab And TRAstuzumab (CLEOPATRA) trial established the combination of pertuzumab, trastuzumab and docetaxel as standard first-line therapy for human epidermal growth factor receptor 2 (HER2)-positive locally recurrent/metastatic breast cancer (LR/mBC). The multicentre single-arm PERtUzumab global SafEty (PERUSE) study assessed the safety and efficacy of pertuzumab and trastuzumab combined with investigator-selected taxane in this setting. Patients and methods: Eligible patients with inoperable HER2-positive LR/mBC and no prior systemic therapy for LR/mBC (except endocrine therapy) received docetaxel, paclitaxel or nab-paclitaxel with trastuzumab and pertuzumab until disease progression or unacceptable toxicity. The primary endpoint was safety. Secondary endpoints included progression-free survival (PFS) and overall survival (OS). Prespecified subgroup analyses included subgroups according to taxane, hormone receptor (HR) status and prior trastuzumab. Exploratory univariable analyses identified potential prognostic factors; those that remained significant in multivariable analysis were used to analyse PFS and OS in subgroups with all, some or none of these factors. Results: Of 1436 treated patients, 588 (41%) initially received paclitaxel and 918 (64%) had HR-positive disease. The most common grade 653 adverse events were neutropenia (10%, mainly with docetaxel) and diarrhoea (8%). At the final analysis (median follow-up: 5.7 years), median PFS was 20.7 [95% confidence interval (CI) 18.9-23.1] months overall and was similar irrespective of HR status or taxane. Median OS was 65.3 (95% CI 60.9-70.9) months overall. OS was similar regardless of taxane backbone but was more favourable in patients with HR-positive than HR-negative LR/mBC. In exploratory analyses, trastuzumab-pretreated patients with visceral disease had the shortest median PFS (13.1 months) and OS (46.3 months). Conclusions: Mature results from PERUSE show a safety and efficacy profile consistent with results from CLEOPATRA and median OS exceeding 5 years. Results suggest that paclitaxel is a valid alternative to docetaxel as backbone chemotherapy. Exploratory analyses suggest risk factors that could guide future trial design

Event recognition - multivariate analysis methods to tag b quark events in ALEPH

The present analysis is devoted to interdiscourse functions in argumentative activities in psychological consulting on radio. The interdiscourse participates in persuasive premises by introducing sentences in relation to doxa and the topic, and the audience or the clients'reactions. it also occurs in interpretative activities according to the psychological consulting's pattern and contributes to creating vulgates in relation to stabilized theories

Innovative Core Design for Generation IV Sodium-Cooled Fast Reactors

The design of innovative cores for Generation IV Sodium-cooled Fast Reactors (SFRs) must chiefly focus on improving safety performance levels and competitiveness, with the aim of achieving all fundamental goals set for Generation IV systems. In this context, one priority is to create a core design such that, in the event of a serious accident, all risks of generalised fuel meltdown are avoided. The core must therefore be optimised to reduce the sodium void reactivity effect whilst acting as a self-converter with respect to the fuel itself. Design options are compared by using the physical sensitivity and parametric studies that were carried out, in order to highlight the most attractive approach for meeting the goals. A very large number of combinations of theses design options are possible For a high power EFR-type core (1500 MWe) with Oxide fuel (UO2-PuO2), the goals can be met, with the sodium void effects nearly halved, to a value of around 3 to 4 dollars, by selecting options, such as: - a tight grid assembly design, - introduction of a sodium plenum in the assembly's upper section, - introduction of a moderator material. Use of a denser fuel such as Carbide is shown to be very attractive. Its higher density means that a near-zero Internal Breeding Gain can be achieved. Most importantly, its thermal conductivity, which is significantly higher than that of the oxide fuel allows for optimisation options. Either the overall core volume can be reduced by increasing linear power density, or the margin between fuel operating temperature and melting point can be increased. Some resuls from core simulations are presented. Further studies should focus on a detailed characterisation of the selected cores, in particular involving ULOF and UTOP type accident transient calculations. These analyses alone will be suitable arbitrators to identify the real safety level achieved

Neutronic benchmark on the 2400 MW gas-cooled fast reactor design

International audienceThe 2400 MWth Gas-Cooled Fast Reactor (GCFR), with plate-type carbide/SiC CERCER fuel, is an innovative design exhibiting many attractive features among which sustainability achieved with an internal breeding gain close to zero and feedback coefficients enabling an excellent behavior under some safety transients. This paper summarizes the analytical results of an international benchmark exercise being set up within the European Union to verify the neutronic tools and associated nuclear data libraries currently used for helping in finalizing the design of the GCFR within the European Union. A rather simple homogenized 2D model has been specified for the first phase of this benchmark. The computational tools being used in the analysis include both a stochastic and a deterministic code, MCNP and ERANOS, respectively, with nuclear data essentially based on the JEF-2.2 data library. The overall results indicate that the agreement of the solutions provided by the different participants is satisfactory. The most significant discrepancy, which can be partly attributed to different ERANOS options, is observed in the case of the end of life reactivity and amounts to a few dollars. The rather positive outcome of this initial phase of the benchmark has allowed identifying deficiencies in the analytical tools and serves as a basis for the definition of subsequent phases. It might also help to identify potential ways to improve the design

The PHENIX Final Tests

The 250 MWe (140 MWe since 1993) PHENIX sodium cooled fast reactor was shut down on March 6th, 2009. Before decommissioning, a final set of tests were performed during the May 2009 – January 2010 period covering core physics, fuel behaviour and thermalhydraulics areas. Detailed analysis of the tests results is ongoing. It will be used for the extension of the validation of ERANOS and DARWIN codes for core physics, TRIO_U and CATHARE for thermalhydraulics and GERMINAL for fuel behaviour. In addition, the program included two tests related to the comprehension of the four negative reactivity transients (AURN in French acronym) experienced during the reactor operation in ‘89 and ‘90 and not yet fully explained. This was also a great opportunity to involve young engineers in the different processes like the design of the tests, their carrying out, and the analysis of the results. The standard instrumentation of the reactor was completed by specifically designed devices