Identifying the research, advocacy, policy and implementation needs for the prevention and management of respiratory syncytial virus lower respiratory tract infection in low- and middle-income countries

Introduction: The high burden of respiratory syncytial virus (RSV) infection in young children disproportionately occurs in low- and middle-income countries (LMICs). The PROUD (Preventing RespiratOry syncytial virUs in unDerdeveloped countries) Taskforce of 24 RSV worldwide experts assessed key needs for RSV prevention in LMICs, including vaccine and newer preventive measures. Methods: A global, survey-based study was undertaken in 2021. An online questionnaire was developed following three meetings of the Taskforce panellists wherein factors related to RSV infection, its prevention and management were identified using iterative questioning. Each factor was scored, by non-panellists interested in RSV, on a scale of zero (very-low-relevance) to 100 (very-high-relevance) within two scenarios: (1) Current and (2) Future expectations for RSV management. Results: Ninety questionnaires were completed: 70 by respondents (71.4% physicians; 27.1% researchers/scientists) from 16 LMICs and 20 from nine high-income (HI) countries (90.0% physicians; 5.0% researchers/scientists), as a reference group. Within LMICs, RSV awareness was perceived to be low, and management was not prioritised. Of the 100 factors scored, those related to improved diagnosis particularly access to affordable point-of-care diagnostics, disease burden data generation, clinical and general education, prompt access to new interventions, and engagement with policymakers/payers were identified of paramount importance. There was a strong need for clinical education and local data generation in the lowest economies, whereas upper-middle income countries were more closely aligned with HI countries in terms of current RSV service provision. Conclusion: Seven key actions for improving RSV prevention and management in LMICs are proposed

Improvement of thermal and epithermal neutron scattering data for the integral measurements interpretation

Dans ces travaux de thèse, la diffusion thermique des neutrons pour l’application aux réacteurs à eau légère a été étudiée. Le modèle de loi de diffusion thermique de l’hydrogène lié à la molécule d’eau de la bibliothèque de données nucléaires JEFF-3.1.1 est basée sur des mesures expérimentales réalisées dans les années soixante. La physique de diffusion de neutrons de cette bibliothèque a été comparée à un modèle basé sur les calculs de dynamique moléculaire développé au Centre Atomique de Bariloche (Argentine), à savoir le modèle CAB. L’impact de ces modèles a également été évalué sur le programme expérimental MISTRAL (configurations UOX et MOX) réalisé dans le réacteur de puissance nulle EOLE situé au CEA Cadarache (France). La contribution de la diffusion thermique des neutrons sur l’hydrogène dans l’eau a été quantifiée sur le calcul de la réactivité et sur l’erreur de calcul du coefficient de température isotherme (reactivity temperature Coefficient en anglais - RTC).Pour le réseau UOX, l’écart entre la réactivité calculée à 20 °C avec le modèle CAB et celle du JEFF-3.1.1 est de +90 pcm, tandis que pour le réseau MOX, il est de +170 pcm à cause de la sensibilité élevée de la diffusion thermique pour ce type de combustible. Dans la plage de température de 10 °C à 80 °C, l’erreur de calcul sur le RTC est de -0.27 ± 0.3 pcm/°C avec JEFF-3.1.1 et de +0.05 ± 0.3 pcm/°C avec le modèle CAB pour le réseau UOX. Pour la configuration MOX, il est de -0.98 ± 0.3 pcm/°C et -0.72 ± 0.3 pcm/°C obtenu respectivement avec la bibliothèque JEFF-3.1.1 et avec le modèle CAB. Les résultats montrent l’apport du modèle CAB dans le calcul de ce paramètre de sureté.In the present report it was studied the neutron thermal scattering of light water for reactors application. The thermal scattering law model of hydrogen bounded to the water molecule of the JEFF-3.1.1 nuclear data library is based on experimental measures performed in the sixties. The scattering physics of this latter was compared with a model based on molecular dynamics calculations developed at the Atomic Center in Bariloche (Argentina), namely the CAB model. The impact of these models was evaluated as well on reactor calculations at cold conditions. The selected benchmark was the MISTRAL program (UOX and MOX configurations), carried out in the zero power reactor EOLE of CEA Cadarache (France). The contribution of the neutron thermal scattering of hydrogen in water was quantified in terms of the difference in the calculated reactivity and the calculation error on the isothermal reactivity temperature coefficient (RTC). For the UOX lattice, the calculated reactivity with the CAB model at 20 °C is +90 pcm larger than JEFF-3.1.1, while for the MOX lattice is +170 pcm because of the high sensitivity of thermal scattering to this type of fuels. In the temperature range from 10 °C to 80 °C, the calculation error on the RTC is -0.27 ± 0.3 pcm/°C and +0.05 ± 0.3 pcm/°C obtained with JEFF-3.1.1 and the CAB model respectively (UOX lattice). For the MOX lattice, is -0.98 ± 0.3 pcm/°C and -0.72 ± 0.3 pcm/°C obtained with the JEFF-3.1.1 library and with the CAB model respectively. The results illustrate the improvement of the CAB model in the calculation of this safety parameter

Towards a covariance matrix of CAB model parameters for H(H

Preliminary results on the uncertainties of hydrogen into light water thermal scattering law of the CAB model are presented. It was done through a coupling between the nuclear data code CONRAD and the molecular dynamic simulations code GROMACS. The Generalized Least Square method was used to adjust the model parameters on evaluated data and generate covariance matrices between the CAB model parameters

Towards a covariance matrix of CAB model parameters for H(H2O)

Preliminary results on the uncertainties of hydrogen into light water thermal scattering law of the CAB model are presented. It was done through a coupling between the nuclear data code CONRAD and the molecular dynamic simulations code GROMACS. The Generalized Least Square method was used to adjust the model parameters on evaluated data and generate covariance matrices between the CAB model parameters

Study on neutron scattering in light water

It is presented a method to produce covariance matrices of the light water total cross section from thermal scattering laws of the JEFF-3.1.1 nuclear data library and CAB model. The generalized least square method was used to fit the LEAPR module parameters of the processing tool NJOY with light water experimental transmission measurements at 293.6K with CONRAD code. The marginalization technique was applied to account for systematic uncertainties

Study on neutron scattering in light water

It is presented a method to produce covariance matrices of the light water total cross section from thermal scattering laws of the JEFF-3.1.1 nuclear data library and CAB model. The generalized least square method was used to fit the LEAPR module parameters of the processing tool NJOY with light water experimental transmission measurements at 293.6K with CONRAD code. The marginalization technique was applied to account for systematic uncertainties

Measurement of double differential cross-section of light water at high temperature and pressure to generate S(α,β)

International audienceA series of double differential inelastic scattering cross-section measurements were performed on light water at several temperatures and pressures using high resolution time-of-flight inelastic spectrometers namely the IN4c and the IN6 at the Institut Laue-Langevin (ILL), Grenoble, France to investigate the impact of temperature and pressure on S(q,ω) and thus S(α,β) thermal scattering kernel. The present work aims at extending previous measurements with light water at room temperature and pressure to more realistic normal operating conditions in connection with nuclear power reactor

Measurement of double differential cross-section of light water at high temperature and pressure to generate S(α,β)

A series of double differential inelastic scattering cross-section measurements were performed on light water at several temperatures and pressures using high resolution time-of-flight inelastic spectrometers, namely the IN4c and the IN6 at the Institut Laue-Langevin (ILL), Grenoble, France to investigate the impact of temperature and pressure on S(q,ω) and thus on the S(α, β) thermal scattering kernel. The present work aims at extending previous measurements with light water at room temperature and pressure to more realistic operating conditions in connection with nuclear power reactors

Measurement of double differential cross-section of light water at high temperature and pressure to generate S(α,β)

A series of double differential inelastic scattering cross-section measurements were performed on light water at several temperatures and pressures using high resolution time-of-flight inelastic spectrometers, namely the IN4c and the IN6 at the Institut Laue-Langevin (ILL), Grenoble, France to investigate the impact of temperature and pressure on S(q,ω) and thus on the S(α, β) thermal scattering kernel. The present work aims at extending previous measurements with light water at room temperature and pressure to more realistic operating conditions in connection with nuclear power reactors