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Review of FUNFI poster session
A.A.Ivanov
Conceptual design studies1. Hagnestal Uppsala University,
SwedenCoil system for a mirror based hybrid reactor
2. Anikeev Novosibirsk state University, Novosibirsk, Russia
Optimisation of the neutron source based on gas dynamic trap for transmutation of radioactive wastes
3.Yurov Budker Institute, Novosibirsk, Russia
Parametrs optimization in a fission-fussion system with a mirror machine based neutron source
4.Beklemishev Budker Institute, Novosibirsk, Russia
GDT-based neutron source with multiple mirror plugs
5. Moiseenko Institute plasma physics, Kharkiv, Ukraine
Fusion neutron generation in a stellarator-mirror hybrid with neutral beam injection
6 Zeng Institute plasma physics, Hefei, China
CAD-based $D neutronics simulation software for fussion, fission and hybrid systems
Diagnostics1Univ. Milano-Bicocca, Milano, Italy. Giacomelli
Univ. Milano-Bicocca, Milano, Italy
Diamond detectors for beam monitors of fast neutron sources
2. Croci IFP-CNR, Milano, Italy A new GEM based neutron diagnostic concept for high power deuterium beams
3. Nocente Univ. Milano-Bicocca, Milano, Italy
Neutron sensitivity and gamma ray measurement in fussion environment
Fuel cycles and development scenarios
1. Ciotti ENEA Frascatti, Italy Italian hybrid and fission reactors scenario analysis
2. McNamara Leabrook cK NEST security treaty:A nuclear energy security treaty.Separating nuclear energy from nuclear weapons.
3. Moiseenko Institute Plasma Physics, Kharkiv, Ukraine
A fuel fo sub-critical fast reactors
Theory1. Agren Uppsala University,
SwedenRadial drift waves invariant in long and thin mirrors
Italian Hybrid and Fission Scenario Analysis M. Ciottia, J. Manzanob, M. Sepiellib
ha ENEA CR Frascati, Via Enrico Fermi, 45, 00044, Frascati, Roma, ItalybENEA 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 A new GEM based neutron diagnostic concept
for high flux neutron beamsfor high flux neutron beams
G.Croci1, M.Rebai2, M.Dalla Palma3, G.Gervasini1, G.Grosso1, F.Murtas4, G. Claps4, R.Pasqualotto3, E.Perelli Cippo2, M.Tardocchi1, M.Tollin3 and G.Gorini1,2
1IFP-CNR, Milano - 2Università di Milano-Bicocca - 3Consorzio RFX–Euratom-ENEA Association, Padova - 4LNF-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/m2) 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.
2Active Area: 35.2 x 19 cm2
CH2/Al Converter Cathode
Padded readout anode (pad area 20x22
mm2)Neutron detection efficiency around 5*10-6
Employed Gas Mixture Ar/CO2 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 (CH2-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). CH2 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 Te~ 3.5 keV
GDT long 2x4 m
GDT KA (Improved)
Psuppl; MW 50 50 150 120
Pnusefull, MW * 0.44 * 1.4 * 4 * 6.5
Sn , neutron/s * 2х1017 * 6.4x1017 * 1.8х1018 * 2 x 1018
Pfis , MW (total) 87 288 1044 1100
Pelout , МW (η=40%) 35 115 418 440
Qel= Pelout / Psuppl; 0.7 2.3 2.8 3.7
MA burning rate, kg/year (1 LWRs = 29 kg / year)
23 (0.8) 75 (2.6) 144 (5) 150 (5)
n-zones
NB injectors
SC magntic coils
D-T plasma
n-zones
NB injectors
SC magntic coils
D-T plasma* Total for ´two sides
Parameter Proof-of-principle scenario
Reactor scenario
Stellarator beta 0.01 0.01
Mirror beta 0.15 0.15
Perpendicular tritium temperature
40 keV 150 keV
Background plasma temperature
400 eV 1.5 keV
Stellarator part magnetic field
2 T 5 T
Mirror ratio 1.5 1.5
Inverse aspect ratio 0.05 0.05
Plasma density 1.21014cm-3 2.11014cm-3
Minority concentration (in mirror part)
0.13 0.13
NBI or RF power 4.3 MW 37 MW
Fission power 28 MW 2.1 GW
Plasma minor radius 17 cm 32 cm
Torus major radius 3.4 m 6.4 m
Mirror length 2.1 m 4 m
Electric efficiency 1.6 14
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)