Review of FUNFI poster session A.A.Ivanov

Conceptual design studies 1. HagnestalUppsala University, Sweden Coil system for a mirror based hybrid reactor 2. AnikeevNovosibirsk state University, Novosibirsk, Russia Optimisation of the neutron source based on gas dynamic trap for transmutation of radioactive wastes 3.YurovBudker Institute, Novosibirsk, Russia Parametrs optimization in a fission- fussion system with a mirror machine based neutron source 4.BeklemishevBudker Institute, Novosibirsk, Russia GDT-based neutron source with multiple mirror plugs 5. MoiseenkoInstitute plasma physics, Kharkiv, Ukraine Fusion neutron generation in a stellarator-mirror hybrid with neutral beam injection 6 ZengInstitute plasma physics, Hefei, China CAD-based $D neutronics simulation software for fussion, fission and hybrid systems

Diagnostics 1Univ. Milano-Bicocca, Milano, Italy. Giacomelli Univ. Milano-Bicocca, Milano, Italy Diamond detectors for beam monitors of fast neutron sources 2. CrociIFP-CNR, Milano, ItalyA new GEM based neutron diagnostic concept for high power deuterium beams 3. NocenteUniv. Milano-Bicocca, Milano, Italy Neutron sensitivity and gamma ray measurement in fussion environment

Fuel cycles and development scenarios 1. CiottiENEA Frascatti, ItalyItalian hybrid and fission reactors scenario analysis 2. McNamaraLeabrook cKNEST security treaty:A nuclear energy security treaty.Separating nuclear energy from nuclear weapons. 3. MoiseenkoInstitute Plasma Physics, Kharkiv, Ukraine A fuel fo sub-critical fast reactors

Theory 1. AgrenUppsala University, SwedenRadial drift waves invariant in long and thin mirrors

Italian Hybrid and Fission Scenario Analysis M. Ciotti a, J. Manzano b, M. Sepielli b h a ENEA CR Frascati, Via Enrico Fermi, 45, 00044, Frascati, Roma, Italy b ENEA CR casaccia, Via Anguillarese, 301, 00123, Santa Maria di Galeria, Roma, Italy Four different scenarios related to the installation of eight EPR reactors in order to evaluate the impact of the SNF repository according to different strategies have been analyzed The advantages of burning the SNF in a fusion-fission hybrid reactor are demonstrated in terms of radiotoxicity and heat decay reduction. For the first the ore level can be reached in around 700 years instead of several hundred thousands of the once through cycle, in the second a site volume reduction of two orders of magnitude can be obtained. The possibility to transmute fertile elements into fissile has been evaluated opening also the possibility for increased independency from raw materials in energy production, assuring a higher degree of confidence in energy affordability. A typical HR would fulfil the Italian needs in terms of reprocessing TRU or for fissile material production for the Th cycle.

A new GEM based neutron diagnostic concept for high flux neutron beams G.Croci 1, M.Rebai 2, M.Dalla Palma 3, G.Gervasini 1, G.Grosso 1, F.Murtas 4, G. Claps 4, R.Pasqualotto 3, E.Perelli Cippo 2, M.Tardocchi 1, M.Tollin 3 and G.Gorini 1,2 1 IFP-CNR, Milano - 2 Università di Milano-Bicocca - 3 Consorzio RFX–Euratom-ENEA Association, Padova - 4 LNF-INFN, Frascati Fig 1: a) Scheme of the Spider Facility; b) Top view of the spider beam dump and of the deuterium beamlets impinging on it: the green boxes are the detectors; c) Contour plot of the power density (MW/m 2 ) profile of a 5X16 beamlets matrix. a) b) c) Fusion-fission hybrid reactors will need high flux neutron detectors to diagnose the deuterium-tritium fusion plasmas as well as the fission reactions. New high flux neutron monitors based on GEM detectors are being developed for application to the ITER neutral beam test facility under construction in Padova. Two experimental devices are being built: SPIDER, a 100 kV negative hydrogen/deuterium RF source, and MITICA, a full scale, 1 MeV deuterium beam injector. 2  Active Area: 35.2 x 19 cm 2  CH 2 /Al Converter Cathode  Padded readout anode (pad area 20x22 mm 2 )  Neutron detection efficiency around 5*10 -6  Employed Gas Mixture Ar/CO 2 70%-30% in Volume  Counting Rate ≈5 kHz  Time resolution < 1 s  Space resolution < 5 mm  Gamma and X-Rays background suppression  Possibility to detect a 10% change in the neutron emission from individual beamlets  Main Information: Map of the deuterium beamlets intensity, derived from the neutron emission map with a suitable unfolding algorithm. nGEM (CH 2 -Cathode) Features and Performances for SPIDER Fig. 2:Microscopic view of a GEM foil. Fig. 3: Schematic view of a Triple-GEM detector and its operation principle Fig. 6: Simulation of energy deposited by protons generated by neutron conversion for different neutron incidence angle (θn). CH 2 thickness = Al thickness = 50 μm 3 4

Optimisation Of The Neutron Source Based On Gas Dynamic Trap For Transmutation Of Radioactive Wastes Poster No. 3 is presented by A. Anikeev The poster presents different versions of the GDT-based neutron source for hybrid fusion- fission sub-critical system for the MA burning. : Source: GDT basic GDT basic T e ~ 3.5 keV GDT long 2x4 m GDT KA (Improved) P suppl ; MW P n usefull, MW * 0.44 * 1.4 * 4 * 6.5 S n, neutron/s * 2х10 17 * 6.4x10 17 * 1.8х10 18 * 2 x P fis, MW (total) P el out, МW (η=40%) Q el = P el out / P suppl ; MA burning rate, kg/year (1 LWRs = 29 kg / year) 23 (0.8)75 (2.6)144 (5)150 (5) * Total for ´two sides

ParameterProof-of- principle scenario Reactor scenario Stellarator beta0.01 Mirror beta0.15 Perpendicular tritium temperature 40 keV150 keV Background plasma temperature 400 eV1.5 keV Stellarator part magnetic field 2 T5 T Mirror ratio1.5 Inverse aspect ratio0.05 Plasma density 1.2  cm  cm -3 Minority concentration (in mirror part) 0.13 NBI or RF power4.3 MW37 MW Fission power28 MW2.1 GW Plasma minor radius17 cm32 cm Torus major radius3.4 m6.4 m Mirror length2.1 m4 m Electric efficiency1.614 Fusion neutron flux Fission reactor Background plasma Mirror part Stellarator part NBI Neutron capturer Magnetic coils Combined mirror-stellarator hybrid Neutron output localized at mirror part Two-component plasma regime allows to generate neutrons both in small and big devices Better power efficiency owing to background plasma confinement in stellarator Continuous operation

Neutron emission level was determined for the source configuration with characteristics close to the limiting ones. Flat maximum of emission power is achieved while varying emission zone length. Fuel blanket multiplicity dependence on buffer zone thickness was calculated for a lead-bismuth eutectic as a buffer zone filler material. It was determined during the numerical experiment, that multiplicity coefficient has a maximum value in the case of buffer zone removal. Main results of GDT-hybrid optimization (P4)