Simulations and experimental studies of the neutronic characteristics of a subcritical system fed by an external source
Creators
- Plaschy, Michael1
- Faculte Sciences de Base, Ecole Polytechnique Federale de Lausanne - EPFL, Institut de physique de l'energie et des particules, Section de physique (Switzerland)
- Commissariat a l'energie atomique et aux energies alternatives - CEA-Cadarache, Service de Physique des Reacteurs et du Cycle, Service d'etudes Physiques EXperimentales (France)
- Institut Paul Scherrer/Paul Scherrer Institut - PSI, Forschungsstrasse 111, 5232 Villigen (Switzerland)
- 1. Ecole Polytechnique Federale de Lausanne - EPFL, Institut de physique de l'energie et des particules, Section de physique (Switzerland)
Description
One of the principal research axes related to nuclear energy concerns the management of nuclear wastes. In this context, certain innovative pathways are being explored to provide options which could lead to a major reduction of the quantities of radioactive nuclides requiring long-term geological storage. An important aspect is the development of advanced nuclear systems which allow the transmutation of long-lived minor actinides, the ADS (accelerator driven system) concept often being proposed for the purpose. Various important developments are necessary for these new systems, one of the principal needs being the qualification of calculational tools to enable the reliable design of an ADS demonstrator. In the present research, related numerical and experimental studies have been carried out in the framework of the MUSE4 program, which was developed on the MASURCA facility at Cadarache, France. This program consists of investigations of a reference critical configuration (MOX fuel with sodium), and several subcritical configurations driven by an external neutron source. The source is obtained with the help of a deuteron accelerator, called GENEPI, which produces neutrons via a nuclear reaction, either with a tritium target (14.1 MeV neutrons), or with a deuterium target (2.7 MeV neutrons). The experimental techniques implemented in this research address the study of spectral variations via foil activation measurements near interfaces characteristic of ADSs. The additional value of such experimental results, compared to standard fission rate traverses obtained using fission chambers (which were also analysed), has been highlighted. An important novel set of integral parameters has thus been made available for the validation of different numerical codes and nuclear data. The activation and fission rate measurements carried out, as also experimental results for other parameters such as keff, βeff and φ*, have been interpreted using various calculational codes (mainly ERANOS and MCNP) and several different nuclear data libraries (JEF-2.2, ERALIB1, ENDF/B6v2). Supplementary information on the performance of the calculational methods has been obtained in the context of the MUSE4 benchmark exercise, conducted by the NEA. The present investigations have led to the resolution of various problems encountered during the earlier MUSE3 program at MASURCA, viz. uncertainties related to description of the intrinsic source description, difficulties in interpreting fission traverses near the external source, etc. A detailed study has thus been made possible of the important factors which characterise subcritical fast systems driven by an external source, i.e. influence of the subcriticality level and of the external source intensity. The various analyses carried out have permitted to establish several recommendations concerning the modeling of the external source and the accelerator tube, as well as the most appropriate numerical methods and data sets to be applied. In this context, the specificity of subcritical configurations, as regards the prediction of parameters such as spatial indices and absolute reaction rates, has been clearly brought out. Certain difficulties (interpretation of high threshold reactions, absolute flux determination, etc.) have thereby been highlighted, pointing at the need for further numerical and experimental investigations. Finally, some recent ERANOS developments have allowed a study to be carried out of the representativity of MUSE4 configurations with respect to alternative ADS concepts proposed in the framework of the international PDS-XADS project. In brief, the representativity of the MUSE4 configurations is found to be quite satisfactory for XADS-Na and XADS-gas. However, in the case of the XADS-Pb/Bi system, effects of the significant uncertainties associated with the nuclear data of lead and bismuth have been clearly highlighted, indicating the desirability of new, more specific experiments for XADS-Pb/Bi validation. (author)
Abstract (French)
L'un des axes de recherche principaux associe a l'energie nucleaire concerne la gestion des dechets nucleaires. Dans ce contexte, des voies innovantes sont explorees afin de fournir des options dont l'objectif est de reduire de maniere significative les quantites des dechets radioactifs a longue duree de vie qui doivent etre stockes. Un aspect important est l'elaboration de systemes nucleaires avances qui permettraient de transmuter les actinides mineurs a longue periode. Pour cela, le concept d'ADS ('accelerator driven system') est souvent avance. Le developpement de ces nouvelles installations impose d'importants developpements, comme, en particulier, un travail de qualification des outils de calcul pour permettre la realisation des etudes de projet, etudes indispensables afin d'aboutir a une definition fiable d'un demonstrateur. Dans la presente recherche, des etudes experimentales et numeriques ont ete menees dans le cadre du programme MUSE4, qui a ete developpe sur l'installation MASURCA de Cadarache. Ce programme se propose d'etudier une configuration critique rapide de reference (combustible de type MOX-sodium), et quelques configurations sous-critiques alimentees par une source neutronique externe. Cette source est obtenue a l'aide d'un accelerateur de deutons, appele GENEPI, qui produit des neutrons par reaction nucleaire avec soit une cible de tritium (neutrons de 14.1 MeV), soit une cible de deuterium (neutrons de 2.7 MeV). Les techniques experimentales mises en place dans ce travail concernent l'etude des variations spectrales aux interfaces caracteristiques des ADSs par l'activation d'echantillons avec ou sans seuil de reaction. L'apport de ce genre de mesures par rapport aux traverses de taux de fission standards, qui furent aussi interpretees, a ete mis en evidence. Ainsi, un ensemble significatif de donnees integrales a ete rendu disponible pour etudier la validite de differents codes de calcul et de donnees nucleaires. Les mesures de taux d'activation et de fission effectuees, ainsi que d'autres resultats experimentaux (keff, βeff, φ*) ont ete interpretes a l'aide de divers codes numeriques (principalement ERANOS et MCNP) et de differentes bibliotheques de donnees nucleaires (JEF-2.2, ERALIB1, ENDF/B6v2). Des informations complementaires sur les performances des schemas de calcul ont aussi ete obtenues dans le cadre du 'benchmark MUSE4', pilote par la NEA. Les investigations realisees ont conduit a la resolution de certaines difficultes rencontrees lors de la phase MUSE3, comme la reduction de l'incertitude sur la connaissance de la source intrinseque et l'amelioration des predictions des traverses de taux de fission proche de la source externe. Ainsi, des etudes detaillees ont pu etre menees afin de soulever l'impact des facteurs d'importance qui caracterisent des systemes rapides sous-critiques alimentes par une source externe, c'est-a-dire l'influence du niveau de sous-criticite et de l'intensite de la source externe. Les differentes analyses effectuees ont aussi permis d'etablir plusieurs recommandations sur la modelisation de la source externe et du tube de l'accelerateur, ainsi que sur l'utilisation de certains schemas de calcul. Dans ce contexte, les specificites des systemes sous-critiques par rapport aux systemes critiques pour la prediction de differents parametres (indices spatiaux, taux de reactions absolus) ont ete clairement elucidees. Ainsi, certaines difficultes sont notamment mises en evidence (interpretation des reactions a haut seuil, determination du flux absolu), qui justifient l'elaboration de futures investigations numeriques et experimentales. Enfin, l'utilisation de developpements recents du formulaire ERANOS a permis d'etablir des facteurs de representativite entre les configurations MUSE4 et les demonstrateurs ADS proposes dans le cadre des etudes internationales PDS-XADS. Pour resumer, la representativite des configurations MUSE4 est, en general, assez satisfaisante avec les systemes XADS-Na et XADS-gaz. Cependant, pour le systeme XADS-Pb/Bi, les effets associes aux fortes incertitudes sur les donnees nucleaires du plomb et du bismuth ont ete clairement mis en evidence, indiquant le besoin d'experiences plus adaptees pour la validation de l'XADS-Pb/Bi. (auteur)Files
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Additional details
Additional titles
- Original title (French)
- Etudes numeriques et experimentales de caracteristiques d'un systeme rapide sous-critique alimente par une source externe
Publishing Information
- Imprint Pagination
- 305 p.
- Report number
- FRCEA-TH--13158
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 52056862
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- ACCELERATOR-DRIVEN SUBCRITICAL SYSTEMS; BENCHMARKS; COMPUTERIZED SIMULATION; DELAYED NEUTRON FRACTION; MASURCA REACTOR; NEUTRON SPECTRA; RADIOACTIVE WASTE PROCESSING; REACTIVITY; VALIDATION
- Descriptors DEC
- AIR COOLED REACTORS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; GAS COOLED REACTORS; MANAGEMENT; PLUTONIUM REACTORS; PROCESSING; RADIOACTIVE WASTE MANAGEMENT; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; SPECTRA; SUBCRITICAL ASSEMBLIES; TESTING; WASTE MANAGEMENT; WASTE PROCESSING; ZERO POWER REACTORS
Optional Information
- Notes
- 129 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses