[{"command":"insert","method":null,"selector":".course-modal-ajax-placeholder-956914","data":"\u003Cdiv class=\u0022container content-rte\u0022\u003E\n  \u003Cdiv class=\u0022row\u0022\u003E\n    \u003Cdiv class=\u0022box col-md-6 bg-primary text-white\u0022\u003E\n      \u003Ch2 class=\u0022h1 text-left\u0022\u003E  Reactor Physics and Simulation\n\u003C\/h2\u003E\n                  \u003Cdiv class=\u0022field-spacing\u0022\u003E\n        \u003Cdiv class=\u0022field__label h3 dash\u0022\u003EECTS :\n          2\n        \u003C\/div\u003E\n      \u003C\/div\u003E\n                  \u003Cdiv class=\u0022field-spacing\u0022\u003E\n        \u003Cdiv class=\u0022field__label h3 dash\u0022\u003ESemester:\n          Semestre 1\n        \u003C\/div\u003E\n      \u003C\/div\u003E\n            \u003Cdiv class=\u0022field-spacing\u0022\u003E\n      \u003Cdiv class=\u0022field__label h3 dash\u0022\u003ED\u00e9tail du volume horaire\u003C\/div\u003E\n                        \u003Cdiv class=\u0022mt-5 text-justify\u0022\u003E\n                          \u003Cspan class=\u0022field__label h4 mt-5 \u0022\u003ELecture:\u003C\/span\u003E\n                                      \u003Cspan\u003E6\u003C\/span\u003E\n                      \u003C\/div\u003E\n                                \u003Cdiv class=\u0022mt-5 text-justify\u0022\u003E\n                          \u003Cspan class=\u0022field__label h4 mt-5 \u0022\u003EPractical study :\u003C\/span\u003E\n                                      \u003Cspan\u003E21\u003C\/span\u003E\n                      \u003C\/div\u003E\n                                                                          \u003C\/div\u003E\n        \u003Cdiv class=\u0022field-spacing\u0022\u003E\n      \u003Cdiv class=\u0022field__label h3 dash\u0022\u003ELangue d\u0026#039;enseignement\u003C\/div\u003E\n                        \u003Cdiv class=\u0022mt-5 text-justify\u0022\u003E\n                                      \u003Cspan\u003EAnglais\u003C\/span\u003E\n                      \u003C\/div\u003E\n                  \u003C\/div\u003E\n        \u003Cdiv class=\u0022field-spacing\u0022\u003E\n      \u003Cdiv class=\u0022field__label h3 dash\u0022\u003EEnseignement \u00e0 distance\u003C\/div\u003E\n                        \u003Cdiv class=\u0022mt-5 text-justify\u0022\u003E\n                                      \u003Cspan\u003Enon\u003C\/span\u003E\n                      \u003C\/div\u003E\n                  \u003C\/div\u003E\n      \u003C\/div\u003E\n    \u003Cdiv class=\u0022box col-md-6\u0022\u003E\n            \u003Cdiv class=\u0022field-spacing\u0022\u003E\n      \u003Cdiv class=\u0022field__label h3 dash\u0022\u003EPr\u00e9requis\u003C\/div\u003E\n                        \u003Cdiv class=\u0022mt-5 text-justify\u0022\u003E\n                                      \u003Cspan\u003E\u003Cp\u003EBasics knowledge acquired in nuclear physics (beta-neutron decay, precursors properties\u2026), Neutronics 1, Thermalhydraulics, PWR Functional Description, Introduction to Safety.\u003C\/p\u003E\u003C\/span\u003E\n                      \u003C\/div\u003E\n                  \u003C\/div\u003E\n        \u003Cdiv class=\u0022field-spacing\u0022\u003E\n      \u003Cdiv class=\u0022field__label h3 dash\u0022\u003EProgramme \/ plan \/ contenus\u003C\/div\u003E\n                        \u003Cdiv class=\u0022mt-5 text-justify\u0022\u003E\n                                      \u003Cspan\u003E\u003Cp\u003EThe module is structured in three parts: a thermo-hydraulic section applied to PWRs, a neutronics and reactor core control section, and an immersive component on the EVOC digital platform (EVOC nuclear system, experimental reactor).\u003C\/p\u003E\u003C\/span\u003E\n                      \u003C\/div\u003E\n                  \u003C\/div\u003E\n        \u003Cdiv class=\u0022field-spacing\u0022\u003E\n      \u003Cdiv class=\u0022field__label h3 dash\u0022\u003EObjectifs d\u0026#039;apprentissage\u003C\/div\u003E\n                        \u003Cdiv class=\u0022mt-5 text-justify\u0022\u003E\n                                      \u003Cspan\u003E\u003Cp\u003EThis course focuses on reactor physics and on the physical, thermal, hydraulic and neutronic phenomena that occur during the operation of nuclear reactors. The use of simulation and modelling enables students to study the couplings between phenomena, to address their dynamic and time-dependent aspects, and to develop a solid understanding of the relevant orders of magnitude.\u003C\/p\u003E\u003C\/span\u003E\n                      \u003C\/div\u003E\n                  \u003C\/div\u003E\n        \u003Cdiv class=\u0022field-spacing\u0022\u003E\n      \u003Cdiv class=\u0022field__label h3 dash\u0022\u003EOrganisation g\u00e9n\u00e9rale et modalit\u00e9s p\u00e9dagogiques\u003C\/div\u003E\n                        \u003Cdiv class=\u0022mt-5 text-justify\u0022\u003E\n                                      \u003Cspan\u003E\u003Cp\u003EDescribe the thermo-hydraulic behaviour of the primary circuit of a PWR under normal and accidental operating conditions, and break down the main steps of the start-up sequence.\u003Cbr\u003E\nDescribe the phases of the accidents studied on the simulator.\u003Cbr\u003E\nExplain the physical phenomena governing the evolution of the system and justify the actions of the reactor protection system.\u003Cbr\u003E\nUse steam tables.\u003Cbr\u003E\nPerform energy and mass balances.\u003C\/p\u003E\n\u003Cp\u003EFor reactor kinetics and xenon\/samarium poisoning, be able to develop a model:\u003Cbr\u003E\n\u2022 Write the systems of differential equations, providing the physical meaning of each term.\u003Cbr\u003E\n\u2022 Derive numerical values for the model from nuclear data and reactor-specific information.\u003C\/p\u003E\n\u003Cp\u003EExplain the Nordheim function and its graphical representation: vertical asymptotes, oblique asymptote, and intersections with both axes.\u003Cbr\u003E\nUse the Nordheim curve to qualitatively and quantitatively describe the kinetic behaviour of the reactor in the following cases: reactor trip (SCRAM), negative reactivity step (rod-drop test), positive reactivity pulse.\u003C\/p\u003E\n\u003Cp\u003EDescribe the kinetic behaviour of the reactor at low flux during the subcritical approach, the evolution of flux near criticality, and the divergence phase.\u003C\/p\u003E\n\u003Cp\u003EPresent the time evolution of xenon and samarium poisoning, with correct orders of magnitude (in time constants and pcm), in the following situations: start-up with fresh or spent fuel, SCRAM, negative power step (load reduction).\u003C\/p\u003E\n\u003Cp\u003EExplain the influence of fuel burnup on xenon and samarium poisoning phenomena.\u003C\/p\u003E\n\u003Cp\u003EExplain the phenomenology of spatial\u2013temporal xenon oscillations in a PWR. Present the influence of the key parameters: geometric dimensions, flux level, presence of MOX fuel, Doppler effect, and power distribution within the core.\u003C\/p\u003E\n\u003Cp\u003EAnalyse transients taking into account the temperature effects of both moderator and fuel in a PWR.\u003C\/p\u003E\n\u003Cp\u003EPerform reactivity balances for a PWR with correct orders of magnitude in different operating conditions: reactor start-up and power ramp-up, power transients.\u003C\/p\u003E\n\u003Cp\u003ENote: Numerical method issues (implicit vs. explicit method, choice of time step) will be discussed during the course but are not defined as learning outcomes.\u003C\/p\u003E\u003C\/span\u003E\n                      \u003C\/div\u003E\n                  \u003C\/div\u003E\n        \u003Cdiv class=\u0022field-spacing\u0022\u003E\n      \u003Cdiv class=\u0022field__label h3 dash\u0022\u003EModalit\u00e9s p\u00e9dagogiques particuli\u00e8res\u003C\/div\u003E\n                        \u003Cdiv class=\u0022mt-5 text-justify\u0022\u003E\n                                      \u003Cspan\u003E\u003Cp\u003EThe specific tools used are:\u003Cbr\u003E\n\u2022 SOFIA PWR simulator\u003Cbr\u003E\n\u2022 C-PWR PWR simulator: temperature effects\u003Cbr\u003E\n\u2022 JANIS: used for searching nuclear data (cross sections, fission yields, decay periods)\u003Cbr\u003E\n\u2022 National Nuclear Data Center NuDat 2.8: search for nuclear data (Sn, Q values for the study of delayed-neutron emission)\u003Cbr\u003E\n\u2022 DESMOS: online function-analysis software, used for manipulating the Nordheim function\u003Cbr\u003E\n\u2022 Software developed at INSTN: Prke, XesmCalc, DiffTools, Sph\u00e8re\u003C\/p\u003E\n\u003Cp\u003EThe module alternates short course refreshers (15-minute segments), demonstrations, hands-on practical work carried out by the students, and guided exercises.\u003C\/p\u003E\u003C\/span\u003E\n                      \u003C\/div\u003E\n                  \u003C\/div\u003E\n        \u003Cdiv class=\u0022field-spacing\u0022\u003E\n      \u003Cdiv class=\u0022field__label h3 dash\u0022\u003EComp\u00e9tences\u003C\/div\u003E\n                        \u003Cdiv class=\u0022mt-5 text-justify\u0022\u003E\n                                      \u003Cspan\u003E\u003Cp\u003E\u2013 Identify the different functionalities of research reactors\u003Cbr\u003E\n\u2013 Analyse the operation of research reactors\u003Cbr\u003E\n\u2013 Know how to start up a research reactor of the ISIS type while complying with safety rules\u003Cbr\u003E\n\u2013 Describe the role of delayed neutrons in reactor kinetics\u003Cbr\u003E\n\u2013 Explain the reactivity changes induced by temperature effects and by modifications of the moderation ratio\u003C\/p\u003E\u003C\/span\u003E\n                      \u003C\/div\u003E\n                  \u003C\/div\u003E\n        \u003Cdiv class=\u0022field-spacing\u0022\u003E\n      \u003Cdiv class=\u0022field__label h3 dash\u0022\u003EBibliographie\u003C\/div\u003E\n                        \u003Cdiv class=\u0022mt-5 text-justify\u0022\u003E\n                                      \u003Cspan\u003E\u003Cp\u003E\u00ab Neutron physics \u00bb (Paul Reuss)\u003C\/p\u003E\n\u003Cp\u003E\u00ab Physics of nuclear kinetics \u00bb (G. Robert Keepin, 1965)\u003C\/p\u003E\n\u003Cp\u003E\u00ab Dynamics of nuclear reactors \u00bb (David L. Hetrick)\u003C\/p\u003E\n\u003Cp\u003E\u00ab Beta-delayed neutron emission evaluation \u00bb (IAEA Headquaters, Vienna, Austria, 10-12 october 2011):\u003C\/p\u003E\n\u003Cp\u003Ehttps:\/\/inis.iaea.org\/collection\/NCLCollectionStore\/_Public\/43\/041\/43041197.pdf?r=1\u0026amp;r=1\u003C\/p\u003E\n\u003Cp\u003E\u00ab Delayed neutron data for the major actinides \u00bb (NEA\/WPEC-6, 2002):\u0026nbsp;\u003C\/p\u003E\n\u003Cp\u003Ehttps:\/\/www.oecd-nea.org\/science\/wpec\/volume6\/volume6.pdf\u003C\/p\u003E\u003C\/span\u003E\n                      \u003C\/div\u003E\n                  \u003C\/div\u003E\n        \u003Cdiv class=\u0022field-spacing\u0022\u003E\n      \u003Cdiv class=\u0022field__label h3 dash\u0022\u003ENature de l\u0026#039;\u00e9valuation\u003C\/div\u003E\n                        \u003Cdiv class=\u0022mt-5 text-justify\u0022\u003E\n                                      \u003Cspan\u003EEvaluation Continue non Int\u00e9grale\u003C\/span\u003E\n                      \u003C\/div\u003E\n                  \u003C\/div\u003E\n      \u003C\/div\u003E\n  \u003C\/div\u003E\n\u003C\/div\u003E\n","settings":null}]