Transcript Review of FUNFI poster session

Review of FUNFI poster session
A.A.Ivanov
Conceptual design studies
1. Hagnestal
Uppsala University,
Sweden
Coil 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 fissionfussion 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
Diagnostics
1Univ. 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
Theory
1. Agren
Uppsala University, Sweden Radial 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, Italy
bENEA
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.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
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.
b)
a)
c)
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.
nGEM (CH2-Cathode) Features and
Performances for SPIDER
Active Area: 35.2 x 19 cm2
4
2
 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.
Fig. 2:Microscopic view of a GEM foil.
3
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
Fig. 3: Schematic view of a Triple-GEM detector and its operation principle
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 fusionfission sub-critical system for the MA burning. :
Source:
Psuppl; MW
Pnusefull, MW
Sn , neutron/s
GDT
basic
GDT basic
Te~ 3.5 keV
GDT long
2x4 m
GDT KA
(Improved)
50
50
150
120
* 0.44
*
1.4
* 2х1017
* 6.4x1017
*
4
* 1.8х1018
*
*
6.5
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
23 (0.8)
75 (2.6)
144 (5)
150 (5)
MA burning rate, kg/year
(1 LWRs = 29 kg / year)
* Total for ´two sides
NB injectors
D-T plasma
n-zones
SC magntic coils
Combined mirror-stellarator hybrid
NBI
Fission
reactor
Proof-ofprinciple
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
2T
5T
Mirror ratio
1.5
1.5
Inverse aspect ratio
0.05
0.05
1.21014cm-3
2.11014cm-3
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
4m
1.6
14
Parameter
Neutron
capturer
Fusion
neutron flux
Background plasma
Stellarator
part
Mirror part
Plasma density
Magnetic coils
•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
Minority concentration
(in mirror part)
Electric efficiency
Main results of GDT-hybrid optimization (P4)
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.