Conference
Conventional fast neutron flux measurements in the radial piercing channel D of the TRIGA Mark II reactor, Pavia.
| العنوان: | Conventional fast neutron flux measurements in the radial piercing channel D of the TRIGA Mark II reactor, Pavia. |
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| المؤلفون: | Marco Di Luzio, Giancarlo D'Agostino, Setareh Fatemi, Barbara Smilgys, Michele Prata, Andrea Salvini, Massimo Oddone, Saverio Altieri |
| المساهمون: | Nuclear Society of Slovenia, Di Luzio, Marco, D'Agostino, Giancarlo, Fatemi, Setareh, Smilgys, Barbara, Prata, Michele, Salvini, Andrea, Oddone, Massimo, Altieri, Saverio |
| بيانات النشر: | Nuclear Society of Slovenia SVN Lubjana |
| سنة النشر: | 2020 |
| المجموعة: | IRIS UNIPV (Università degli studi di Pavia) |
| مصطلحات موضوعية: | fast neutron flux measurement, TRIGA Mark II reactor, Pavia |
| الوصف: | The TRIGA Mark II nuclear reactor operated by the Laboratory of Applied Nuclear Energy (LENA) of the University of Pavia is a 250 kW light water moderated facility aimed for training, general purpose research and isotope production [1]. One of the research fields conducted at this reactor is focused on the investigation of nuclear reactions induced by fast neutrons. The accessibility to a fast neutron beam allows a broad variety of applications, ranging from the determination of fast neutron cross section data, study of burnup and transmutation in fuel elements and effects of radiation damage in various materials; all these applications might be, in turn, beneficial for what concerns research and development of the upcoming IV generation of fast nuclear reactors. In order to make available a fast neutron beam at the TRIGA reactor, the realization of a new neutron irradiation facility is planned by modifying the so-called channel D, a pre-existing radial piercing channel without reflector material. The channel D will be adapted by introducing filters to remove the neutron thermal flux component and reduce the gamma background, and a beam catcher to assure operator’s safety. Characteristics and dimensions of filtering and shielding materials will be modulated according to the neutron flux spectra simulated by means of Monte Carlo Neutron Particle (MCNP) software. The quality of the simulated data will be assured by validating the software code using experimental data collected in selected positions along the channel. In this study, preliminary measurements of conventional fast neutron flux in four positions of the actual (unmodified) configuration of channel D are reported. The adopted technique, described in [2], consists of activations and ?-countings of monitor elements. The resulting fast neutron flux relies on a conventional value of the monitor fission-neutron averaged cross section, ?. Ni solutions, obtained from a Ni solid standard dissolved in nitric acid, were selected as monitors to exploit the ... |
| نوع الوثيقة: | conference object |
| وصف الملف: | STAMPA |
| اللغة: | English |
| Relation: | ispartofbook:Book of Abstracts NENE2020 29th lnternational Conference Nuclear Energy for New Europe; NENE2020 29th lnternational Conference Nuclear Energy for New Europe; firstpage:308; lastpage:309; numberofpages:2; http://hdl.handle.net/11571/1345434 |
| الاتاحة: | http://hdl.handle.net/11571/1345434 |
| رقم الانضمام: | edsbas.D6505173 |
| قاعدة البيانات: | BASE |
| الوصف غير متاح. |