exotic nuclei structure and reaction noyaux exotiques ... - IPN - IN2P3
exotic nuclei structure and reaction noyaux exotiques ... - IPN - IN2P3 exotic nuclei structure and reaction noyaux exotiques ... - IPN - IN2P3
simulation of flow is based on three or four partial differential equations: conservation of mass, energy and momentum vector for the water liquid/ vapor mixture (optionally a fourth equation can be added which tracks the vapor mass separately). The heat transfer model features a full boiling curve, comprising the basic heat transfer regimes: single phase forced convection, sub-cooled nucleate boiling, saturated nucleate boiling, transition and film boiling. Heat conduction in the fuel, gap and cladding is calculated using the balance equation. To obtain a realistic description of a coupled neutronics/thermal-hydraulics system, a number of iterations with upgrades of data are blies. Inlet pressure is also uniform 15.5 MPa. All radial and axial powers are normalized to average value. A uniform core flow of 82.12 kg/s/assembly is assumed. For each assembly, there are three types of pins: UOX, UOX + IFBA (IFBA is burnable absorber: necessary to obtain converged results. The number of iterations required for a fixed number of Monte-Carlo histories depends on the specific details of each system. The more the system is asymmetric the greater the number of iterations required. For a pressurized water reactor (e.g. PWR), such as the one used for the benchmark (see below), less than ten iterations are needed. For a fast reactor (e.g. SFR), fewer than five are needed, and for a boiling water reactor (e.g. BWR) in which the void fraction has a huge gradient with correspondingly large changes in the flux more than ten iterations are needed for convergence. To validate the 3D coupling MURE-MCNP/ COBRA, a PWR MOX/UO2 NEA benchmark has been chosen 10 . It presents a large heterogeneity which permits a rigorous test of the coupling. Four degrees of enrichment are present in the fuel with seven different levels of fuel depletion. Some fuel pins contain integrated burnable poisons. All of these aspects strongly affect the flux profile, which will be highly asymmetric. The MURE coupling allows heterogeneous axial and radial fuel compositions. However in this benchmark the core axial material compositions are assumed to be homogeneous. The benchmark for four assemblies is presented in the next section. The quarter core used for the benchmark has been cut. It correspond to the assemblies A1 (top left – burn-up 35 GWd/t), A2 (top right – burn-up 0.15 GWd/t), B1 (bottom left – burn-up 0.15 GWd/t) and B2 (bottom right – 17.5 GWd/t). Consequently reflective conditions are imposed on lateral boundaries, and void is assumed on extreme axial planes (zero flux). Coolant inlet temperature is uniform for all assem- zirconium diboride ZrB 2 , cf. fig. 10), and guide tubes. Similar pins have been grouped together to accelerate the calculation. The choice of these cell groups have been performed for neighboring cells, and cells which are exposed to similar fluxes. A sample of the benchmark results are shown in Figs. 4 & 5. All results of axial power deposition are in good agreement (less than 1%) with the other simulations of the benchmark. Results of the coupled calculation MURE-MCNP/COBRA are in agreement with benchmark results (cf. fig. 12), and the accuracy is within the errors of the benchmark: 2%). Only the four most peripheral pins have a difference of 4% in our calculation. These are the most difficult to simulate, due to the assumption of reflective conditions. 121
Fission cross sections of actinides at nTOF, from resonances to spallation IPNO Participation: L. Tassan-Got, L. Audouin, C. Paradela, C.-O. Bacri, C. Stéphan, B. Berthier, D. Tarrio, D. Trubert, C. Le Naour Mesures de sections efficaces de fission à nTOF, des résonances à la spallation Le faisceau de neutrons de l’installation nTOF du CERN offre des possibilités uniques : gamme en énergie étendue (0.7eV à 1GeV), très bonne résolution en énergie des neutrons, haut flux instantané particulièrement utile pour les cibles radioactives. Nous avons mesuré les sections efficaces de fission par détection en coincidence des fragments de fission, ce qui permet d’éliminer la contribution des autres types de réaction à haute énergie, et réduit le bruit de fond de radioactivité. Les isotopes pour lesquelles les mesures ont été effectuées sont 232 Th, 233 U et 234 U jouant un rôle important dans le cycle du thorium, 237 Np comme cible possible de l’incinération, ainsi que nat Pb et 209 Bi qui interviennent dans les cibles de spallation. Toutes les mesures ont été effectuées relativement à 235 U et 238 U considérés comme références. Pour le 237 Np nous trouvons une section efficace de fission supérieure à celle des bases de données. Nuclear reaction data for minor actinides play a key role in the development of a new generation of nuclear reactors. The aim for future reactors is to significantly reduce nuclear waste radiotoxicity through partitioning and transmutation techniques, thereby decreasing the repository needs for highlevel radioactive waste. Recently, to fulfil the data requirements for these new reactors, there has been a demand for extensive neutron-induced nuclear cross section measurements for actinides. Inside this line we measured the fission cross section of 234 U and 237 Np. The incineration of 237 Np, one of the more abundant isotopes in the spent fuel from current reactors, is an important issue in transmutation. 234 U plays an important role for the development of the thorium cycle, where it acts as an analogue to 240 Pu in the Pu/U cycle of the present-day fast reactors. Most previous measurements of these isotopes were performed a few decades ago in limited neutron energy ranges. nat Pb and 209 Bi play a key role in accelerator driven systems (ADS) since the spallation target will most likely consist of lead or lead-bismuth. In addition 209 Bi(n, f) has been recommended as a crosssection standard for neutron energies above 50 MeV but new measurements are needed. The very broad energy range (thermal to 1 GeV) of neutrons delivered at the nTOF facility at CERN allowed accurate measurements of the fission cross sections of 233 U, 234 U, 237 Np, nat Pb and 209 Bi. They all have been performed in reference to 235 U and 238 U permanently present in the stack of targets. . The detection system was built in order to detect the 2 fragments in coincidence and hence discriminate fission events from other types of reaction : radioactivity, recoils of reactions appearing at energies above 10 MeV, and spallation reactions at a few tens of MeV. The experimental setup is made of a stack of 10 parallel plate avalanche counters (PPAC) interleaved with 9 targets including the 2 reference isotopes. The ambiguities arising from the possible crossing of 2 detectors by the same fission fragments are solved by the coincidence time between detectors. Fig. 1. Fission yields ratios between different samples of the same isotope, normalized by the actinide content. The ratio between the two 234 U samples is shown by the dotted line with symbols, while the ratios between the 237 Np samples and their average are indicated by solid colored lines. The detailed characteristics of the targets are described in [1]. They are made by electrodeposition on a 2 µm thick aluminium foil, over a disk of 8 cm in diameter. The content of the deposited layer has been obtained by α counting with an accuracy better than 1 %, and the spatial distribution has also been scanned by α counting and by the RBS technique. Due to pile-up problems, localisation measurement could not be used for a systematic monitoring of the detector acceptance. Therefore the cross sections measurement rely only on the coincidences of the fast anode signals. The detection efficiency is mainly determined by the limitation of the solid angle resulting from the stopping of the fission fragments in the backing and the PPAC electrodes when the fission angle is higher than 50°. The thicknesses of the stopping layers being very simi- 122
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Fission cross sections of actinides at nTOF,<br />
from resonances to spallation<br />
<strong>IPN</strong>O Participation: L. Tassan-Got, L. Audouin, C. Paradela, C.-O. Bacri, C. Stéphan, B. Berthier, D.<br />
Tarrio, D. Trubert, C. Le Naour<br />
Mesures de sections efficaces de fission à nTOF, des résonances à la spallation<br />
Le faisceau de neutrons de l’installation nTOF du CERN offre des possibilités uniques : gamme en énergie<br />
étendue (0.7eV à 1GeV), très bonne résolution en énergie des neutrons, haut flux instantané particulièrement<br />
utile pour les cibles radioactives. Nous avons mesuré les sections efficaces de fission par détection<br />
en coincidence des fragments de fission, ce qui permet d’éliminer la contribution des autres types<br />
de réaction à haute énergie, et réduit le bruit de fond de radioactivité. Les isotopes pour lesquelles les<br />
mesures ont été effectuées sont 232 Th, 233 U et 234 U jouant un rôle important dans le cycle du thorium,<br />
237 Np comme cible possible de l’incinération, ainsi que nat Pb et 209 Bi qui interviennent dans les cibles de<br />
spallation. Toutes les mesures ont été effectuées relativement à 235 U et 238 U considérés comme références.<br />
Pour le 237 Np nous trouvons une section efficace de fission supérieure à celle des bases de données.<br />
Nuclear <strong>reaction</strong> data for minor actinides play a<br />
key role in the development of a new generation of<br />
nuclear reactors. The aim for future reactors is to<br />
significantly reduce nuclear waste radiotoxicity<br />
through partitioning <strong>and</strong> transmutation techniques,<br />
thereby decreasing the repository needs for highlevel<br />
radioactive waste.<br />
Recently, to fulfil the data requirements for these<br />
new reactors, there has been a dem<strong>and</strong> for extensive<br />
neutron-induced nuclear cross section measurements<br />
for actinides. Inside this line we measured<br />
the fission cross section of 234 U <strong>and</strong> 237 Np. The<br />
incineration of 237 Np, one of the more abundant<br />
isotopes in the spent fuel from current reactors, is<br />
an important issue in transmutation. 234 U plays an<br />
important role for the development of the thorium<br />
cycle, where it acts as an analogue to 240 Pu in the<br />
Pu/U cycle of the present-day fast reactors. Most<br />
previous measurements of these isotopes were<br />
performed a few decades ago in limited neutron<br />
energy ranges.<br />
nat Pb <strong>and</strong> 209 Bi play a key role in accelerator driven<br />
systems (ADS) since the spallation target will most<br />
likely consist of lead or lead-bismuth. In addition<br />
209 Bi(n, f) has been recommended as a crosssection<br />
st<strong>and</strong>ard for neutron energies above 50<br />
MeV but new measurements are needed.<br />
The very broad energy range (thermal to 1 GeV) of<br />
neutrons delivered at the nTOF facility at CERN<br />
allowed accurate measurements of the fission<br />
cross sections of 233 U, 234 U, 237 Np, nat Pb <strong>and</strong> 209 Bi.<br />
They all have been performed in reference to 235 U<br />
<strong>and</strong> 238 U permanently present in the stack of targets.<br />
.<br />
The detection system was built in order to detect<br />
the 2 fragments in coincidence <strong>and</strong> hence discriminate<br />
fission events from other types of <strong>reaction</strong> :<br />
radioactivity, recoils of <strong>reaction</strong>s appearing at energies<br />
above 10 MeV, <strong>and</strong> spallation <strong>reaction</strong>s at a<br />
few tens of MeV. The experimental setup is made<br />
of a stack of 10 parallel plate avalanche counters<br />
(PPAC) interleaved with 9 targets including the 2<br />
reference isotopes. The ambiguities arising from<br />
the possible crossing of 2 detectors by the same<br />
fission fragments are solved by the coincidence<br />
time between detectors.<br />
Fig. 1. Fission yields ratios between different samples of the<br />
same isotope, normalized by the actinide content. The ratio<br />
between the two 234 U samples is shown by the dotted line with<br />
symbols, while the ratios between the 237 Np samples <strong>and</strong> their<br />
average are indicated by solid colored lines.<br />
The detailed characteristics of the targets are described<br />
in [1]. They are made by electrodeposition<br />
on a 2 µm thick aluminium foil, over a disk of 8 cm<br />
in diameter. The content of the deposited layer has<br />
been obtained by α counting with an accuracy better<br />
than 1 %, <strong>and</strong> the spatial distribution has also<br />
been scanned by α counting <strong>and</strong> by the RBS technique.<br />
Due to pile-up problems, localisation measurement<br />
could not be used for a systematic monitoring of<br />
the detector acceptance. Therefore the cross sections<br />
measurement rely only on the coincidences<br />
of the fast anode signals. The detection efficiency<br />
is mainly determined by the limitation of the solid<br />
angle resulting from the stopping of the fission<br />
fragments in the backing <strong>and</strong> the PPAC electrodes<br />
when the fission angle is higher than 50°. The<br />
thicknesses of the stopping layers being very simi-<br />
122