Departament de Física i Enginyeria Nuclear (fins octubre 2015)
http://hdl.handle.net/2117/3983
Sun, 21 Jan 2018 20:50:45 GMT2018-01-21T20:50:45ZMeasurement of the neutron capture cross section of the fissile isotope 235U with the CERN n TOF total absorption calorimeter and a fission tagging based on micromegas detectors
http://hdl.handle.net/2117/112986
Measurement of the neutron capture cross section of the fissile isotope 235U with the CERN n TOF total absorption calorimeter and a fission tagging based on micromegas detectors
Balibrea-Correa, J.; Mendoza, E.; Cano-Ott, D; Calviño Tavares, Francisco; Cortés Rossell, Guillem Pere; Gómez Hornillos, María Belén; Riego Pérez, Albert
The accuracy on neutron capture cross section of fissile isotopes must be improved for the design of future nuclear systems such as Gen-IV reactors and Accelerator Driven Systems. The High Priority Request List of the Nuclear Energy Agency, which lists the most important nuclear data requirements, includes also the neutron capture cross sections of fissile isotopes such as 233,235U and 239,241Pu.
A specific experimental setup has been used at the CERN n TOF facility for the measurement of the neutron capture cross section of 235U by a set of micromegas fission detectors placed inside a segmented BaF2 Total Absorption Calorimeter.
Fri, 19 Jan 2018 12:55:30 GMThttp://hdl.handle.net/2117/1129862018-01-19T12:55:30ZBalibrea-Correa, J.Mendoza, E.Cano-Ott, DCalviño Tavares, FranciscoCortés Rossell, Guillem PereGómez Hornillos, María BelénRiego Pérez, AlbertThe accuracy on neutron capture cross section of fissile isotopes must be improved for the design of future nuclear systems such as Gen-IV reactors and Accelerator Driven Systems. The High Priority Request List of the Nuclear Energy Agency, which lists the most important nuclear data requirements, includes also the neutron capture cross sections of fissile isotopes such as 233,235U and 239,241Pu.
A specific experimental setup has been used at the CERN n TOF facility for the measurement of the neutron capture cross section of 235U by a set of micromegas fission detectors placed inside a segmented BaF2 Total Absorption Calorimeter.New measurement of the 242Pu(n,gamma) cross section at n TOF-EAR1 for MOX fuels: Preliminary results in the RRR
http://hdl.handle.net/2117/112969
New measurement of the 242Pu(n,gamma) cross section at n TOF-EAR1 for MOX fuels: Preliminary results in the RRR
Lerendegui-Marco, J.; Guerrero, C.; Cortés-Giraldo, M.A.; Calviño Tavares, Francisco; Casanovas Hoste, Adrià; Cortés Rossell, Guillem Pere; Gómez Hornillos, María Belén; Tarifeño Saldivia, Ariel Esteban
The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined with 238U to make mixed oxide (MOX) fuel. In this way the Pu from spent fuel is used in a new reactor cycle, contributing to the long-term sustainability of nuclear energy. The use of MOX fuels in thermal and fast reactors requires accurate capture and fission cross sections. For the particular case of 242Pu, the previous neutron capture cross section measurements were made in the 70’s, providing an uncertainty of about 35% in the keV region. In this context, the Nuclear Energy Agency recommends in its “High Priority Request List” and its report WPEC-26 that the capture cross section of 242Pu should be measured with an accuracy of at least 7–12% in the neutron energy range between 500 eV and 500 keV. This work presents a brief description
of the measurement performed at n TOF-EAR1, the data reduction process and the first ToF capture
measurement on this isotope in the last 40 years, providing preliminary individual resonance parameters
beyond the current energy limits in the evaluations, as well as a preliminary set of average resonance
parameters.
Fri, 19 Jan 2018 11:20:26 GMThttp://hdl.handle.net/2117/1129692018-01-19T11:20:26ZLerendegui-Marco, J.Guerrero, C.Cortés-Giraldo, M.A.Calviño Tavares, FranciscoCasanovas Hoste, AdriàCortés Rossell, Guillem PereGómez Hornillos, María BelénTarifeño Saldivia, Ariel EstebanThe spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined with 238U to make mixed oxide (MOX) fuel. In this way the Pu from spent fuel is used in a new reactor cycle, contributing to the long-term sustainability of nuclear energy. The use of MOX fuels in thermal and fast reactors requires accurate capture and fission cross sections. For the particular case of 242Pu, the previous neutron capture cross section measurements were made in the 70’s, providing an uncertainty of about 35% in the keV region. In this context, the Nuclear Energy Agency recommends in its “High Priority Request List” and its report WPEC-26 that the capture cross section of 242Pu should be measured with an accuracy of at least 7–12% in the neutron energy range between 500 eV and 500 keV. This work presents a brief description
of the measurement performed at n TOF-EAR1, the data reduction process and the first ToF capture
measurement on this isotope in the last 40 years, providing preliminary individual resonance parameters
beyond the current energy limits in the evaluations, as well as a preliminary set of average resonance
parameters.Monte Carlo simulations for the study of a moderated neutron detector
http://hdl.handle.net/2117/104373
Monte Carlo simulations for the study of a moderated neutron detector
Gómez Hornillos, María Belén; Gorlychev, V.; Caballero Folch, Roger; Cortés Rossell, Guillem Pere; Poch Parés, Agustí; Pretel Sánchez, Carme; Calviño Tavares, Francisco
This work presents the Monte Carlo simulations performed with the MCNPX and GEANT4 codes for the design of a BEta deLayEd Neutron detector, BELEN-20. This detector will be used for the study of beta delayed neutron emission and consists of a block of polyethylene with dimensions 90x90x80 cm3 and 20 cylindrical 3He gas counters. The results of these simulations have been validated experimentally with a 252Cf source in the laboratory at UPC, Barcelona. Also the first experiment with this detector has been carried out in November 2009 in JYFL, Finland. In this experiment the neutron emission probability after beta decay of the fission products 88Br, 94;95Rb, and 138I has been measured; this data is still under analysis. Simulations with MCNPX and GEANT4 have been performed in order to obtain the efficiency of the BELEN-20 detector for each of the above nuclei using the neutron energy distribution corresponding to each nucleus.
Fri, 12 May 2017 12:49:41 GMThttp://hdl.handle.net/2117/1043732017-05-12T12:49:41ZGómez Hornillos, María BelénGorlychev, V.Caballero Folch, RogerCortés Rossell, Guillem PerePoch Parés, AgustíPretel Sánchez, CarmeCalviño Tavares, FranciscoThis work presents the Monte Carlo simulations performed with the MCNPX and GEANT4 codes for the design of a BEta deLayEd Neutron detector, BELEN-20. This detector will be used for the study of beta delayed neutron emission and consists of a block of polyethylene with dimensions 90x90x80 cm3 and 20 cylindrical 3He gas counters. The results of these simulations have been validated experimentally with a 252Cf source in the laboratory at UPC, Barcelona. Also the first experiment with this detector has been carried out in November 2009 in JYFL, Finland. In this experiment the neutron emission probability after beta decay of the fission products 88Br, 94;95Rb, and 138I has been measured; this data is still under analysis. Simulations with MCNPX and GEANT4 have been performed in order to obtain the efficiency of the BELEN-20 detector for each of the above nuclei using the neutron energy distribution corresponding to each nucleus.Dynamic study of a supercritical carbon dioxide power cycle for DEMO
http://hdl.handle.net/2117/100014
Dynamic study of a supercritical carbon dioxide power cycle for DEMO
Batet Miracle, Lluís; Linares, José Ignacio; Aulet Prieto, David; Cantizano González, Alexis; Griñó Cubero, Robert; Moratilla, Beatriz Y.
In the framework of the research program undertaken by the EUROFusion consortium (within H2020), the feasibility has been analysed of using a supercritical carbon dioxide Brayton cycle as the power conversion system in a future fusion nuclear reactor with breeding blankets of the type Dual Coolant Lithium-Lead. The integration in the layout of the thermal sources has been optimized and thermal energy storage has been featured in order to decouple the reactor operation from the power generation.
Dynamic modelling of the selected design has been performed with the thermal-hydraulic system code RELAP5-3D. Presently the model only includes the CO2 cycle, and the circuits of fluids exchanging heat directly with the cycle, along with all the needed heat exchangers.
The code allows the simulation of control systems. Control strategies aimed to stabilize some plant parameters have been implemented.
Wed, 25 Jan 2017 11:49:05 GMThttp://hdl.handle.net/2117/1000142017-01-25T11:49:05ZBatet Miracle, LluísLinares, José IgnacioAulet Prieto, DavidCantizano González, AlexisGriñó Cubero, RobertMoratilla, Beatriz Y.In the framework of the research program undertaken by the EUROFusion consortium (within H2020), the feasibility has been analysed of using a supercritical carbon dioxide Brayton cycle as the power conversion system in a future fusion nuclear reactor with breeding blankets of the type Dual Coolant Lithium-Lead. The integration in the layout of the thermal sources has been optimized and thermal energy storage has been featured in order to decouple the reactor operation from the power generation.
Dynamic modelling of the selected design has been performed with the thermal-hydraulic system code RELAP5-3D. Presently the model only includes the CO2 cycle, and the circuits of fluids exchanging heat directly with the cycle, along with all the needed heat exchangers.
The code allows the simulation of control systems. Control strategies aimed to stabilize some plant parameters have been implemented.Development and assessment of fire-related risk unavailability matrices to support the application of the maintenance rule in a PWR nuclear power plant
http://hdl.handle.net/2117/88442
Development and assessment of fire-related risk unavailability matrices to support the application of the maintenance rule in a PWR nuclear power plant
Díaz Bayona, Pedro; Estruch Traveria, Enric; Dies Llovera, Javier; Tapia Fernández, Carlos; Blas Del Hoyo, Alfredo de; Asamoah, Matthew
Two methods are presented which serve to incorporate the fire-related risk into the current practices in nuclear power plants with respect to the assessment of configurations. The development of these methods is restricted to the compulsory use of fire probabilistic safety assessment (PSA) models. The first method is a fire protection systems and key safety functions unavailability matrix which is developed to identify structures, systems, and components significant for fire-related risk. The second method is a fire zones and key safety functions (KSFs) fire risk matrix which is useful to identify fire zones which are candidates for risk management actions. Specific selection and quantification methodologies have been developed to obtain the matrices. The Monte Carlo method has been used to assess the uncertainty of the unavailability matrix. The analysis shows that the uncertainty is sufficiently bounded. The significant fire-related risk is localized in six KSF representative components and one fire protection system which should be included in the maintenance rule. The unavailability of fire protection systems does not significantly affect the risk. The fire risk matrix identifies the fire zones that contribute the most to the fire-related risk. These zones belong to the control building and electric penetrations building.
Fri, 01 Jul 2016 08:11:44 GMThttp://hdl.handle.net/2117/884422016-07-01T08:11:44ZDíaz Bayona, PedroEstruch Traveria, EnricDies Llovera, JavierTapia Fernández, CarlosBlas Del Hoyo, Alfredo deAsamoah, MatthewTwo methods are presented which serve to incorporate the fire-related risk into the current practices in nuclear power plants with respect to the assessment of configurations. The development of these methods is restricted to the compulsory use of fire probabilistic safety assessment (PSA) models. The first method is a fire protection systems and key safety functions unavailability matrix which is developed to identify structures, systems, and components significant for fire-related risk. The second method is a fire zones and key safety functions (KSFs) fire risk matrix which is useful to identify fire zones which are candidates for risk management actions. Specific selection and quantification methodologies have been developed to obtain the matrices. The Monte Carlo method has been used to assess the uncertainty of the unavailability matrix. The analysis shows that the uncertainty is sufficiently bounded. The significant fire-related risk is localized in six KSF representative components and one fire protection system which should be included in the maintenance rule. The unavailability of fire protection systems does not significantly affect the risk. The fire risk matrix identifies the fire zones that contribute the most to the fire-related risk. These zones belong to the control building and electric penetrations building.Characterization of a neutron-beta counting system with beta-delayed neutron emitters
http://hdl.handle.net/2117/85596
Characterization of a neutron-beta counting system with beta-delayed neutron emitters
Agramunt Ros, Jorge; Taín, J.L.; Gómez Hornillos, María Belén; Calviño Tavares, Francisco; Cortés Rossell, Guillem Pere; Pretel Sánchez, Carme; Riego Pérez, Albert; Tarifeño Saldivia, Ariel Esteban
A new detection system for the measurement of beta-delayed neutron emission probabilities has been characterized using fission products with well known ß-delayed neutron emission properties. The setup consists of BELEN-20, a 4p neutron counter with twenty 3He proportional tubes arranged inside a large polyethylene neutron moderator, a thin Si detector for ß counting and a self-triggering digital data acquisition system. The use of delayed-neutron precursors with different neutron emission windows allowed the study of the effect of energy dependency on neutron, ß and ß-neutron rates. The observed effect is well reproduced by Monte Carlo simulations. The impact of this dependency on the accuracy of neutron emission probabilities is discussed. A new accurate value of the neutron emission probability for the important delayed-neutron precursor 137I was obtained, Pn=7.76(14)%.
Wed, 13 Apr 2016 10:59:47 GMThttp://hdl.handle.net/2117/855962016-04-13T10:59:47ZAgramunt Ros, JorgeTaín, J.L.Gómez Hornillos, María BelénCalviño Tavares, FranciscoCortés Rossell, Guillem PerePretel Sánchez, CarmeRiego Pérez, AlbertTarifeño Saldivia, Ariel EstebanA new detection system for the measurement of beta-delayed neutron emission probabilities has been characterized using fission products with well known ß-delayed neutron emission properties. The setup consists of BELEN-20, a 4p neutron counter with twenty 3He proportional tubes arranged inside a large polyethylene neutron moderator, a thin Si detector for ß counting and a self-triggering digital data acquisition system. The use of delayed-neutron precursors with different neutron emission windows allowed the study of the effect of energy dependency on neutron, ß and ß-neutron rates. The observed effect is well reproduced by Monte Carlo simulations. The impact of this dependency on the accuracy of neutron emission probabilities is discussed. A new accurate value of the neutron emission probability for the important delayed-neutron precursor 137I was obtained, Pn=7.76(14)%.Fractal structure and predictive strategy of the daily extreme temperature residuals at Fabra Observatory (NE Spain, years 1917-2005)
http://hdl.handle.net/2117/78472
Fractal structure and predictive strategy of the daily extreme temperature residuals at Fabra Observatory (NE Spain, years 1917-2005)
Lana Pons, Francisco Javier; Burgueño, August; Serra de Larrocha, Carina; Martínez Santafé, Maria Dolors
A compilation of daily extreme temperatures recorded at the Fabra Observatory (Catalonia, NE Spain) since 1917 up to 2005 has permitted an exhaustive analysis of the fractal behaviour of the daily extreme temperature residuals, DTR, defined as the difference between the observed daily extreme temperature and the daily average value. The lacunarity characterises the lag distribution on the residual series for several thresholds. Hurst, H, and Hausdorff, Ha, exponents, together with the exponent beta of the decaying power law, describing the evolution of power spectral density with frequency, permit to characterise the persistence, antipersistence or randomness of the residual series. The self-affine character of DTR series is verified, and additionally, they are simulated by means of fractional Gaussian noise, fGn. The reconstruction theorem leads to the quantification of the complexity (correlation dimension, mu*, and Kolmogorov entropy, kappa.) and predictive instability (Lyapunov exponents, lambda, and Kaplan-Yorke dimension, D-KY) of the residual series. All fractal parameters are computed for consecutive and independent segments of 5-year lengths. This strategy permits to obtain a high enough number of fractal parameter samples to estimate time trends, including their statistical significance. Comparisons are made between results of predictive algorithms based on fGn models and an autoregressive autoregressive integrated moving average (ARIMA) process, with the latter leading to slightly better results than the former. Several dynamic atmospheric mechanisms and local effects, such as local topography and vicinity to the Mediterranean coast, are proposed to explain the complex and instable predictability of DTR series. The memory of the physical system (Kolmogorov entropy) would be attributed to the interaction with the Mediterranean Sea.
Thu, 29 Oct 2015 10:50:38 GMThttp://hdl.handle.net/2117/784722015-10-29T10:50:38ZLana Pons, Francisco JavierBurgueño, AugustSerra de Larrocha, CarinaMartínez Santafé, Maria DolorsA compilation of daily extreme temperatures recorded at the Fabra Observatory (Catalonia, NE Spain) since 1917 up to 2005 has permitted an exhaustive analysis of the fractal behaviour of the daily extreme temperature residuals, DTR, defined as the difference between the observed daily extreme temperature and the daily average value. The lacunarity characterises the lag distribution on the residual series for several thresholds. Hurst, H, and Hausdorff, Ha, exponents, together with the exponent beta of the decaying power law, describing the evolution of power spectral density with frequency, permit to characterise the persistence, antipersistence or randomness of the residual series. The self-affine character of DTR series is verified, and additionally, they are simulated by means of fractional Gaussian noise, fGn. The reconstruction theorem leads to the quantification of the complexity (correlation dimension, mu*, and Kolmogorov entropy, kappa.) and predictive instability (Lyapunov exponents, lambda, and Kaplan-Yorke dimension, D-KY) of the residual series. All fractal parameters are computed for consecutive and independent segments of 5-year lengths. This strategy permits to obtain a high enough number of fractal parameter samples to estimate time trends, including their statistical significance. Comparisons are made between results of predictive algorithms based on fGn models and an autoregressive autoregressive integrated moving average (ARIMA) process, with the latter leading to slightly better results than the former. Several dynamic atmospheric mechanisms and local effects, such as local topography and vicinity to the Mediterranean coast, are proposed to explain the complex and instable predictability of DTR series. The memory of the physical system (Kolmogorov entropy) would be attributed to the interaction with the Mediterranean Sea.Aftershock sequences of three seismic crises at southern California, USA, simulated by a cellular automata model based on self-organized criticality
http://hdl.handle.net/2117/78319
Aftershock sequences of three seismic crises at southern California, USA, simulated by a cellular automata model based on self-organized criticality
Monterrubio Velasco, Marisol; Lana Pons, Francisco Javier; Martínez Santafé, Maria Dolors
Several properties of aftershock series related to the main shocks of Landers, Northridge and Hector Mine (southern California, USA) are reproduced by the Dynamic Fiber Bundle Model, DFBM. Optimum values for the three parameters governing DFBM are determined by searching for the best agreement of real aftershock series properties and those of synthetic sequences generated by this model. The analysis of the model parameter values provides details on the underlying physical mechanism of the aftershock sequence generation. First, the ratio of seismic energy radiated as seismic waves and transferred as stress-strain to adjacent faults; second, the degree of stress heterogeneity reproducing the complex behavior of real aftershock series. Additionally, the results of simulations support the coexistence of two types of relaxation processes. One of them is associated with the well-known modified Omori's (MO) law, which involves elapsed times between consecutive aftershocks monotonically increasing; the other is manifested by episodes of sudden stress release, with inter-event times much shorter than those predicted by MO law. These episodes are assumed to be a consequence of the complex distribution of tectonic stresses and fault geometry. The first process is associated to events designed as leading aftershocks, LA. The second process generates series of events which are designed as cascades, CA. It is worth of mention that several properties concerning CAs can be reasonably related to critical changes on stress field along the simulation process.
Tue, 27 Oct 2015 11:12:24 GMThttp://hdl.handle.net/2117/783192015-10-27T11:12:24ZMonterrubio Velasco, MarisolLana Pons, Francisco JavierMartínez Santafé, Maria DolorsSeveral properties of aftershock series related to the main shocks of Landers, Northridge and Hector Mine (southern California, USA) are reproduced by the Dynamic Fiber Bundle Model, DFBM. Optimum values for the three parameters governing DFBM are determined by searching for the best agreement of real aftershock series properties and those of synthetic sequences generated by this model. The analysis of the model parameter values provides details on the underlying physical mechanism of the aftershock sequence generation. First, the ratio of seismic energy radiated as seismic waves and transferred as stress-strain to adjacent faults; second, the degree of stress heterogeneity reproducing the complex behavior of real aftershock series. Additionally, the results of simulations support the coexistence of two types of relaxation processes. One of them is associated with the well-known modified Omori's (MO) law, which involves elapsed times between consecutive aftershocks monotonically increasing; the other is manifested by episodes of sudden stress release, with inter-event times much shorter than those predicted by MO law. These episodes are assumed to be a consequence of the complex distribution of tectonic stresses and fault geometry. The first process is associated to events designed as leading aftershocks, LA. The second process generates series of events which are designed as cascades, CA. It is worth of mention that several properties concerning CAs can be reasonably related to critical changes on stress field along the simulation process.Criticality in the slowed-down boiling crisis at zero gravity
http://hdl.handle.net/2117/78228
Criticality in the slowed-down boiling crisis at zero gravity
Charignon, Thomas; Lloveras Muntané, Pol Marcel; Chatain, Denis; Truskinovsky, Lev; Vives, Eduard; Beysens, Daniel; Nikolayev, Vadim
Boiling crisis is a transition between nucleate and film boiling. It occurs at a threshold value of the heat flux from the heater called CHF (critical heat flux). Usually, boiling crisis studies are hindered by the high CHF and short transition duration (below 1 ms). Here we report on experiments in hydrogen near its liquid-vapor critical point, in which the CHF is low and the dynamics slow enough to be resolved. As under such conditions the surface tension is very small, the experiments are carried out in the reduced gravity to preserve the conventional bubble geometry. Weightlessness is created artificially in two-phase hydrogen by compensating gravity with magnetic forces. We were able to reveal the fractal structure of the contour of the percolating cluster of the dry areas at the heater that precedes the boiling crisis. We provide a direct statistical analysis of dry spot areas that confirms the boiling crisis at zero gravity as a scale-free phenomenon. It was observed that, in agreement with theoretical predictions, saturated boiling CHF tends to zero (within the precision of our thermal control system) in zero gravity, which suggests that the boiling crisis may be observed at any heat flux provided the experiment lasts long enough.
Mon, 26 Oct 2015 12:12:09 GMThttp://hdl.handle.net/2117/782282015-10-26T12:12:09ZCharignon, ThomasLloveras Muntané, Pol MarcelChatain, DenisTruskinovsky, LevVives, EduardBeysens, DanielNikolayev, VadimBoiling crisis is a transition between nucleate and film boiling. It occurs at a threshold value of the heat flux from the heater called CHF (critical heat flux). Usually, boiling crisis studies are hindered by the high CHF and short transition duration (below 1 ms). Here we report on experiments in hydrogen near its liquid-vapor critical point, in which the CHF is low and the dynamics slow enough to be resolved. As under such conditions the surface tension is very small, the experiments are carried out in the reduced gravity to preserve the conventional bubble geometry. Weightlessness is created artificially in two-phase hydrogen by compensating gravity with magnetic forces. We were able to reveal the fractal structure of the contour of the percolating cluster of the dry areas at the heater that precedes the boiling crisis. We provide a direct statistical analysis of dry spot areas that confirms the boiling crisis at zero gravity as a scale-free phenomenon. It was observed that, in agreement with theoretical predictions, saturated boiling CHF tends to zero (within the precision of our thermal control system) in zero gravity, which suggests that the boiling crisis may be observed at any heat flux provided the experiment lasts long enough.A new code for spectrometric analysis for environmental radiological surveillance on monitors focused on a gamma radioactivity on aerosols
http://hdl.handle.net/2117/77887
A new code for spectrometric analysis for environmental radiological surveillance on monitors focused on a gamma radioactivity on aerosols
Blas Del Hoyo, Alfredo de; Riego Pérez, Albert; García Sánchez, Roger; Tapia Fernández, Carlos; Dies Llovera, Javier; Díaz Bayona, Pedro
This paper presents a new code for the analysis of
gamma spectra generated by an equipment for continuous measurement
and identification of gamma radioactivity in aerosols
with paper filter. It is called pGamma and has been developed
by the NERG group at the Technical University of Catalonia
- Barcelona Tech and Raditel Serveis i Subministraments Tecnològics,
Ltd. The code is being adapted to the monitors of the
Environmental Radiological Surveillance Network of the Generalitat
de Catalunya (local Catalan Government), Spain. The code
is a spectrum analysis system for identifying and determining
activity concentration of gamma emitters. It generates alarms
depending on the activity of emitters and then elaborates reports.
Moreover, it includes a library with NORM and artificial emitters
of interest. The code is being used at three stations of the Network
equipped with an aerosol monitor (Ascó and Vandellòs (province
of Tarragona)and Barcelona).
Mon, 19 Oct 2015 14:17:36 GMThttp://hdl.handle.net/2117/778872015-10-19T14:17:36ZBlas Del Hoyo, Alfredo deRiego Pérez, AlbertGarcía Sánchez, RogerTapia Fernández, CarlosDies Llovera, JavierDíaz Bayona, PedroThis paper presents a new code for the analysis of
gamma spectra generated by an equipment for continuous measurement
and identification of gamma radioactivity in aerosols
with paper filter. It is called pGamma and has been developed
by the NERG group at the Technical University of Catalonia
- Barcelona Tech and Raditel Serveis i Subministraments Tecnològics,
Ltd. The code is being adapted to the monitors of the
Environmental Radiological Surveillance Network of the Generalitat
de Catalunya (local Catalan Government), Spain. The code
is a spectrum analysis system for identifying and determining
activity concentration of gamma emitters. It generates alarms
depending on the activity of emitters and then elaborates reports.
Moreover, it includes a library with NORM and artificial emitters
of interest. The code is being used at three stations of the Network
equipped with an aerosol monitor (Ascó and Vandellòs (province
of Tarragona)and Barcelona).