Review of FUNFI poster session A.A.Ivanov. Conceptual design studies 1. HagnestalUppsala University, Sweden Coil system for a mirror based hybrid reactor.

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)