DRIVEN SUBCRITICAL FISSION SYSTEMS USING A CYLINDRICAL INERTIAL ELECTROSTATIC CONFINEMENT (IEC) NEUTRON SOURCE - PowerPoint PPT Presentation

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DRIVEN SUBCRITICAL FISSION SYSTEMS USING A CYLINDRICAL INERTIAL ELECTROSTATIC CONFINEMENT (IEC) NEUTRON SOURCE

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Title: DRIVEN SUBCRITICAL FISSION SYSTEMS USING A CYLINDRICAL INERTIAL ELECTROSTATIC CONFINEMENT (IEC) NEUTRON SOURCE


1
DRIVEN SUBCRITICAL FISSION SYSTEMS USING A
CYLINDRICAL INERTIAL ELECTROSTATIC CONFINEMENT
(IEC) NEUTRON SOURCE
Miley G. H., Thomas R., Takeyama Y., Wu L.,
Percel I., Momota H., Hora H2., Li X. Z3. and P.
J. Shrestha4 1University of Illinois, Urbana,
IL, USA 2University of New South Wales, Sydney,
NSW, Australia 3Tsinghua University, Beijing,
China 4NPL Associates, Inc., Champaign, IL, USA
2
Introduction IEC driven subcritial systems
  • The IEC is already a commercial fusion neutron
    source at low levels!!
  • Replaced Cf-252 in neutron activation analysis
    at
  • Ore mines in Germany
  • Coal mines in USA
  • In these cases ease of licensing, long lived
    target (plasma), on-off capability, simplicity
    of construction (low cost), compactness, low
    maintenance requirement, flexibility in neutron
    spectrum (2.54 or 14 MeV), ease of control gave
    the IEC the edge. The features can carry over
    to a driver for a hybrid.
  • Possibility of small size/power opens door to
    several near term applications university
    training and research facilities.

3
Flexible geometry offers new types of drive
configurations ---
Fig. 1 Spherical IEC Device
Fig. 2 Cylindrical IEC Device
4
Cylindrical IECs
  • Cylindrical IECs offer many advantages for the
    present sub-critical reactor system .
  • The prototype cylindrical IEC version , C-device,
    is a particularly attractive.
  • Deuterium (or D-T) beams in a hollow cathode
    configuration give fusion along the extended
    colliding beam volume in the center of the device
    a line-type neutron source.

5
Figure 3 Diagram of the C-device with calculated
ion trajectories and equi-potential surfaces
6
IEC Modular Cylindrical Design Advantage
  • Accelerator approaches to date have used an
    accelerator spallation-target system.
  • The large size and cost of the accelerator remain
    an issue. Also, the in-core target system poses
    significant design and engineering complications.
  • The IEC fits in fuel element openings of the
    sub-critical core assembly. This provides a
    distributed source of neutrons
  • Replaces both the accelerator system and
    spallation-target by by multiple modular sources
    assembly.
  • Provides flexibility in core design and in flux
    profile control.
  • Small IEC units can be produced at a lower cost
    than the accelerator

7
Vertical Cross-Section Showing C-device Modules
8
Top Cross-Section View Shows C-Device Modules in
Channel Locations
9
IEC Status
  • Considerable research on the IEC concept has
    already been carried out on a laboratory scale
    1012 n/s neutron driver for low power
    sub-assemblies . (student labs or research
    assemblies)
  • A key remaining issue for power reactors or
    actinide burners is concerns the ability to scale
    up to the high neutron rates required using the
    small volume units that are envisioned. Requires
    an intermediate prototype at 1014 n/s,
    followed by a full demo unit at 1018 n/s.
    Modular design allows testing on single small
    units speeding this development up.
  • Engineering issues include materials development
    (common to other drivers), blanket (here core)
    design, rad hardening of the high-voltage
    components.

10
Flowchart of MCP Code used to scale up from
presnt low level devices
11
Neutron Production Fits Reasonably Well With
Earlier Data
12
Neutron source strength predictions
  • Present experiments give 1010 DD n/s (1012 DT
    n/s at 90 kV and 20 mA.
  • Extrapolation to 1014 n/s (prototype research
    reactor goal) at 100 kV requires 0.3 A or 30 kW
    input.
  • With improved potential profile control, might be
    reduced to lt10 kW.
  • Research focusing on power reduction.
  • Further extrapolation to higher power systems
    also promising.

13
Near Term Use in Low Power Research Reactors or
Teaching Labs
  • Present experimental IEC devices are close to
    neutron yields required of this application.
  • Calculations for a representative graphite
    moderated subassembly next.

14
Graphite Modulated Sub-critical System
  • Figure presents the power obtained per unit
    source as a function of the multiplication factor
    k8.
  • assumed to be a cylindrical homogeneous reactor,
    fueled by uranium dioxide.
  • The fuel enrichment is adjusted to give the
    desired value of k8.
  • the fraction of core volume occupied by the fuel
    fixed at 5.
  • the graphite-moderated system can deliver 1 kW of
    power with a source of 1012 neutrons/sec at Keff
    0.99
  • Specifications summarized in Table .

15
Figure 4 Power level per unit source (P/S) as a
function as a function of k? for two different
moderators
16
Table 1 Parameters for a 1 kW graphite-
moderated sub-critical system.
Fuel UO2 (0.5 U-235)
Moderator material Graphite
Moderator volume fraction 95
Multiplication factor 0.97
Radius (cm) Height (cm) 3050
Source strength (neutrons/s) 1x1012
Power (kW) 1.2
17
Summary
  • A 1-kW IEC driven graphite moderated research
    reactor appears attractive from a cost and safety
    point of view.
  • Also, existing experimental IEC devices very
    close to the target of 1012 n/s.
  • This is consistent with the source levels in
    Garching II research reactors (Cf-252 neutron
    source with 4x109 neutrons/sec).

18
Future Driven Reactor Designs vs Accelerator
Target designs
  • Designed to ensure safety against criticality and
    loss-of-cooling accidents as is done in the
    conventional accelerator-target designs.
  • But important differences exist in the method
    used .
  • Accelerator designs use a passive beam shut-off
    device based a combination of thermocouple
    readings and a melt-rupture disk in the side-wall
    of the beam guide tube.
  • The IEC uses a temperature sensitive fuse in the
    in-core electrical circuit to shut down the
    high-voltage.
  • A melt rupture disk on the IEC wall is added as
    backup to spoil the IEC vacuum.
  • A very rough conceptual design for a 1000 MWe
    plant has been developed. The reactor core
    employs distributed IEC units as in the low power
    subcritical applications. Very important here for
    flux profile control.

19
Design RD Comments
  • Cylindrical IEC units occupy multiple fuel
    channels. a distribute d neutron source and
    modular source design.
  • 15 units stacked in each channel in preliminary
    design for 1000Mwe unit.
  • Selected to optimize neutron profiles in both the
    radial and vertical directions
  • This distributed source design is to be
    contrasted to a central core spallation target
    (STET)
  • Waste heat from IEC is deposited on the large
    area hollow electrodes and removed by coolant
    flow around the fuel channels.
  • A keff lt 0.97 requires 1018 n/s per IEC ( vs
    present experimental values of 1012 D-T n/s)
    MCR calculations indicate feasible.
  • Since IEC scaling involves velocity space
    increasing the yield does not require a
    significant increase in unit size.
  • Instead, higher beam currents and improved ion
    recirculation are key other special crucial
    issues include high-voltage stand-offs that are
    radiation hardened. Material development, etc.
    are common issues to other drivers.
  • These issues can be studied starting from a
    simple small unit, allowing a rapid development
    cycle..

20
Conclusions
  • An alternative to the standard driven reactor
    accelerator-spallation target design is proposed
    which employs IEC neutron sources which can be in
    a central location or distributed across a number
    of fuel channels. Such a modular design has
    distinct advantages in reduced driver costs, plus
    added flexibility in optimizing neutron flux
    profiles in the core. The basic physics for the
    IEC has been demonstrated in small-scale
    laboratory experiments, but a scale-up in source
    strength is required for ultimate power reactors.
  • However, the IEC source strength is already near
    the level required for low power research
    reactors or for student sub-critical laboratory
    devices. This application would be advantageous
    since the safety advantages of these reactors
    should enable a next generation of research
    reactors to be constructed quickly, meeting the
    educational and research needs facing us as there
    is a rebirth of interest in nuclear power.
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