The Actual Problems of Microworld Physics
Gomel, Belarus, July 22 - August 2, 2013
The new electro-nuclear method and scheme of energy
production and transmutation of radioactive waste
components of nuclear power
S.Tyutyunnikov
Joint Institute for Nuclear Research, Dubna, Russia
Joint Institute for Nuclear Research, Dubna, Russia;
CPTP «Atomenergomash», Moscow, Russia;
INP, Rez near Praha, Czech Republic;
IAE, Swierk near Warzhawa, Poland;
JIENR Sosny near Minsk, Belarus;
Stepanov IP, Minsk, Belarus
KIPT, Kharkov, Ukraine;
INRNE, Sofiaя, Bulgaria;
ESU, Erevan, Armenia;
Uni-Sydney, Sydney, Australia;
Aristotele Uni-Saloniki, Tessaloniki, Greece;
IPT, Almaty, Kazahstan;
IPT, Ulanbaatar, Mongolia;
INS Vinca, Belgrad, Serbia
Bhabha ARC, Mumbai, India;
Gesellschaft for Kernspektrometrie, Gemany;
Leipunsky IPPE, Obninsk, Russia
FZJ, Julich, Germany
Polytechnic Institute, Praha, Czech Republic;
Dubna University, Dubna, Russia;
IAR AS, Kishinev, Moldova;
UzhNU, Uzhgorod, Ukraine.
Gomel, July 22 - August 2, 2013
Workshop Collaboration “E + T RAW”
(“Energy plus Transmutation of Radioactive Wastes”)
2011, November
Gomel, July 22 - August 2, 2013
Content
 Basic principles of classical nuclear
energy
 Traditional nuclear fission
 ADS technology, the principles,
achievements and prospects
 The physical basis of relativistic nuclear
energy and the experimental results
 Conclusion
Gomel, July 22 - August 2, 2013
Introduction
 Stocks explored oil and gas provide energy fuel
for 30-50 years.
 Explored reserves of coal - for 200-300 years.
 The share of nuclear energy in overall energy
balance of the Earth - 6%.
 Classical nuclear power, founded on the division
of U235, Pb239 has several problems:
 Limited stocks of fissile material - at 20-50 years.
 Continuous operating time of nuclear waste.
Gomel, July 22 - August 2, 2013
Traditional nuclear fission
● Nuclear energy is produced whenever a light nucleus is
undergoing fusion or a heavy nucleus is undergoing fission.
● Today’s nuclear energy is based on U-235, 0.71 % of the natural
Uranium, fissionable both with thermal and with fast neutrons.
● At the present consumption rate (≈6% of primary energy), U
reserves are about comparable with those of Oil and NG.
● In the Sixties, ”Atoms for Peace” had promised cheap, abundant
and universally available nuclear power, where the few “nuclear”
countries would ensure the necessary know-how to the many others
which had renounced nuclear weaponry.
● Today, the situation is far from being universally acceptable: the
link between peaceful and military applications has been shortened
by the inevitable developments and the corresponding widening of
the know-how of nuclear technologies.
● For nuclear energy to become freely and more abundantly
available in all countries, some totally different but adequate
nuclear technology must be developed.
Gomel, July 22 - August 2, 2013
New, virtually unlimited forms of
nuclear energy
● Particularly interesting are fission reactions in which a natural
element is firstly bred into a readily fissionable element.
Energy Amplifier
Gen-IV
● The main advantage of these reactions without U-235 is that they may
offer an essentially unlimited energy supply, during millennia at the
present primary energy level, quite comparable to the one of Lithium
driven D-T Nuclear Fusion.
● However, they require substantial developments since :
➩two neutrons (rather than one) are necessary to close the main cycle
➩the daughter elements (U-233 and/or Pu-239) do not exist in nature
but they can be generated after initiation
Gomel, July 22 - August 2, 2013
• The problems of rapidly growing energy consumption
in the world can not be solved without the use of
nuclear energy.
• The key issue here is the availability of an adequate
supply of nuclear fuel. In the long term aspect, the use
of such materials as enriched 235U or artificial 239Pu can
not solve the problem of global energy.
• Indeed, they receive is very energy intensive, and the
total value is rather limited and certainly does not
exceed the forecast amount of hydrocarbon fuel.
• So only involvement in the production of energy is
practically unlimited reserves of natural (depleted)
uranium and thorium can provide long-term prospects
for nuclear energy.
Gomel, July 22 - August 2, 2013
Structure of an irradiated PWR fuel element
PWR fuel element = 500 kg U before Irradiation
Valuable Materials
Uranium : 475 kg
(95 %)
Plutonium : 5 kg
( 1 %)
HL Waste
Fission Products:
20 kg
(4 %)
Minor Actinides : ~ 500g
(0.1 %)
Gomel, July 22 - August 2, 2013
The unresolved problem of disposing of spent nuclear fuel, containing
the accumulated long-lived radioactive fission products and minor actinides - a
major obstacle for the development of conventional nuclear power.
To date, spent fuel assemblies (FAs) containing spent nuclear fuel, are
not subject to processing, but simply placed in the complex-site storage of
existing nuclear power plants, awaiting the development of effective
technologies for processing and creation of appropriate capacity. The main way
of reducing the activity is implemented simply by their long exposure.
Loading VVER-1000 is ~ 80 t UO2 (~ 70 tons of uranium). Over 60
years of operation one unit will be unloaded ~ 1600 tons of SNF, containing a
total of ~ 16.6 tons of transuranic elements, of which ~ 16.0 tones - the
plutonium isotopes .
With today's technology in the processing of 1 ton of spent nuclear
fuel (about 0.1 m3) produced ~ 45 m3 of liquid high level radioactive waste,
about 150 m3 of medium-and low-level ~ 2000 m3.
In the closed nuclear fuel cycle (not yet implemented) is expected
education annually as a result of processing up to 25 m3/GW high-level waste,
intermediate level and 50-100 m3/GW 700 m3/GWlow-level waste.
The repository is Yucca Mountain (USA), capacity 70 000 tons of spent
nuclear fuel has been allocated ~ 96.2 billion. I.e. cost of SNF is ~ 1374 $/kg
only capital costs, not including transportation and maintenance.
The cost of fuel loading in three years, the VVER-1000 ~ 94 million, or
~1175$/kg.
Thus, the SNF is considerably more expensive than fresh fuel.
Gomel, July 22 - August 2, 2013
Radiotoxicity
√ Direct disposal
of the over
all nuclear wastes
Gomel, July 22 - August 2, 2013
Radiotoxicity
√ Separation and
transmutation of
99.9% of Pu and U
Gomel, July 22 - August 2, 2013
Radiotoxicity
√ Separation and
transmutation of
99.9% of Pu, U and MA
√ Achievement:
Disposal times are
shifted from geological
to historical time scales
in nuclear waste
disposal.
Gomel, July 22 - August 2, 2013
Transmutation with present technology
Fast Reactors
LWR Reactors
Innovative Concepts
Innovative
Gene IV
Reactors
Gomel, July 22 - August 2, 2013
Fundamental, ineradicable weaknesses
of today's nuclear energy technologies:
1) use as nuclear fuel, fissile materials – 235U, in the long term 239Pu
and 233U;
2) work with fission spectrum neutrons (average energy spectrum 2MeV, the maximum - 10 MeV);
and as a result, work on the basis of a controlled fission chain
reaction.
Consequence
Gomel, July 22 - August 2, 2013
Consequence
4 ineradicable in today's nuclear energy technology issues:
1
theoretical possibility of a critical accident;
2
use of working hours and "bomb" material - the actinides,
i.e., problem of non-proliferation;
3
continuous operating time of long-lived radioactive waste;
4
resulting from the first three – the problem of withdrawal power blocks of
modern nuclear power plants
Gomel, July 22 - August 2, 2013
ADS - technology
The physical aspects of electro-nuclear energy production method are
actively studied today in many scientific centers all over the world: USA, Germany,
France, Sweden, Switzerland, Japan, Russia, Belarus, China, India etc. Most
activities are concentrated on the classical electro-nuclear systems – Accelerator
Driven Systems (ADS) – based on spallation neutron generation, with a spectrum
harder than that of fission neutrons, by protons with an energy of about 1 GeV in a
high-Z target. These neutrons can also be used for generating nuclear energy in the
active zone having criticality of 0,94-0,98 and surrounding the target.
The large national projects devoted to the creation of industrial ADS
demonstration prototypes are implemented in Japan (JPARC), USA (RACE), the
joint European project EUROTRNS is carried out.
The main advantage of electro-nuclear technology, as compared to
conventional reactor technologies, is that subcritical active core and external
neutron source (accelerator and neutron-producing target) are used. This advantage
doesn’t provides only intrinsic safety of the system but also makes it possible to
obtain high fluxes of high energy neutrons independent of fission neutrons of the
subcritical assembly material. The high-energy neutrons are an ideal tool to induce
fission in most trans-uranium isotopes and thus transmute most of the dangerous
radioactive waste from nuclear power production and other sources.
Gomel, July 22 - August 2, 2013
Accelerator Driven Systems
Proton (Linear) Accelerator
E ~ 1 GeV, I ~ 15-100 mA
Gomel, July 22 - August 2, 2013
Critical (reactor) and sub-critical (energy amplifier)
operation
Gomel, July 22 - August 2, 2013
The need for a new concept: an Accelerator driven system
● This very small neutron excess is essentially incompatible with the
requirements of any critical reactor without U-235. An external neutron
source must be added to ensure the neutron inventory balance. This is
both true for Fission (Th and/or Depleted U) and D-T Fusion starting
from Lithium.
● The development of modern accelerators has permitted the production
of a substantial neutron flux with the help of a proton driven high energy
spallation source.
● Let Keff be the neutron multiplication coefficient of an ADS (Keff =1 for
a critical reactor). In a “sub-critical” mode, Keff <1 neutrons are produced
by a spallation driven proton beam source and multiplied by fissions. The
nuclear power is then directly proportional to the proton beam power
with a gain G:
G=
χ ≈ 2.1.÷ 2.4 for Pb - p coll. > 0.5 GeV
G = 70-80 for Keff=0.97 and G = 700-800 for Keff = 0.997 (very large)
Gomel, July 22 - August 2, 2013
Problems of natural uranium and
thorium use
• But in this experiment the massive uranium target ( ~3.5 tones) was
embedded into light water moderator. As consequence the neutron
spectrum inside of active core was practically fully thermalized and
neutron multiplicity coefficient Keff this system was near 0.9.
• In these circumstances in spite of rather promising GBP~30 it is
difficult to implement "burning" of the base core material (natural
uranium or thorium) because of their high fission threshold.
• And actually proposed EA options must move on to the enriched
fuel!?
Gomel, July 22 - August 2, 2013
Neutron flux distribution (arbitrary units)
SPATIAL DISTRIBUTION OF THE NEUTRON
FLUX
Distance from the source (mm)
Spatial distribution of the neutron flux
depending on the value of k.
Comparison of the neutron flux
distribution between measured data
and Monte Carlo calculations carried
out in the "source mode" with EAMC
and MCNP-4B, and in the "reactor
mode" with MCNP-4B.
Gomel, July 22 - August 2, 2013
Main result of the FEAT experiment
(S. Andriamonje et al.,CERN/AT/94-45(ET))
Gomel, July 22 - August 2, 2013
A prolific neutron source: the proton spallation in a heavy Z
 Modern proton accelerators on a heavy Z
target (Lead) produce a very large number of
neutrons.
 For a proton energy of 1 GeV and 1.5
GWatt thermal power we need:
➩2.7 1020 fission/s (Keff = 0.997, G=700 )
➩3.8 1017 spallation neutrons/s (30 n/p)
➩1.3 1016 protons/s
➩Current: 2.12 mA
Compare: PSI proton cyclotron:
590 MeV,
72 MeV injection 2mA,
1 MWatt
Gomel, July 22 - August 2, 2013
Accelerator requirements and reliability
● The spallation target is the most innovative element of the
Energy Amplifier.
● High currents are within the possibilities of modern
accelerators, either Cyclotrons or superconducting LINACs.
● Reliability is the most important new aspect of an
otherwise within the state of the art realization.
● It should be easily achieved through redundancy of the
separate components: no more than few beam trips per year
Cyclotron
Gomel, July 22 - August 2, 2013
Principle of operation of the Energy Amplifier
● The process is based on two steps:
➩Non fissile Thorium is transformed into
fissile U-233 with the help of a first
neutron:
➩Fissile U-233 is fissioned by a second
neutron, with large energy production the
emission of 2.3 new additional neutrons
which continue the process.
● A particle accelerator is supplying the
missing neutron fraction and it controls the
energy produced in the reaction.
● At the end of a cycle the fuel is reprocessed
and the only waste are Fission Fragments Their
radio-activity is intense, but limited to some
hundred years.
● Actinides are recovered without separation
and are the “seeds” of the next load, added to
fresh Thorium.
● The cycle is “closed” in the sense that the
only material inflow is the natural element and
the only “outflow” are Fission Fragments.
Gomel, July 22 - August 2, 2013
Gomel, July 22 - August 2, 2013
Gomel, July 22 - August 2, 2013
Motivation of RNT (relativistic nuclear technology)
 ADS is considered now as tool for the transmutation of the
long-lived components of radioactive wastes (RAW) and in
principle for the solution of global energy problems.
 This work is aimed at study of the physicals properties of the
ADS with quasi-infinite size active core (AC) from natural
uranium irradiates by the pulsed p/d beam of (1-10) GeV
energy.
 The long-range goal is the study of the possibilities of such
systems with maximally hard neutron spectrum inside of AC to
realize so called Relativistic Nuclear Technology (RNT) for
transmutation RAW and energy production due to burning of
AC material.
 Important aim of the experimental program is to provide
comprehensive benchmark data set for verification and
adjustment of INC models and transport codes.
Gomel, July 22 - August 2, 2013
Physical basis of relativistic nuclear
technology
Physical substantiation for investigation of new schemes of
electronuclear power production and transmutation of long-lived
radioactive wastes based on nuclear relativistic technologies is
presented. “E + T RAW” (“Energy plus Transmutation of Radioactive
Wastes”) is aimed at complex study of interaction of relativistic
beams of Nuclotron-M with energies up to 10 GeV in quasi-infinite
targets.
Feasibility of application of natural/depleted uranium or
thorium without the use of uranium-235, as well as utilization of
spent fuel elements of atomic power plants is demonstrated based
on analysis of results of known experiments, numerical, and
theoretical works.
“E + T RAW” project will provide fundamentally new data and
numerical methods necessary for design of demonstration
experimental-industrial setups based on the proposed scheme.
Gomel, July 22 - August 2, 2013
Physical basis of relativistic nuclear technology
Energy characteristics of neutron radiation leaving a limited Ø20×60 cm lead target
depending on protons energy
(obtained in the complex experimental group V.I .Yurevich, executed in LHEP)
Here, < Е > is the average neutron energy, Еkin is the total kinetic energy of neutron radiation, Еp is the proton energy, and W
is the energy of the proton beam spent for neutron production.
It can be seen from Table 2 that the average neutron energy, the kinetic neutron energy Еkin, and the proton beam energy W
spent for neutron production increase with increasing beam energy.
The fraction of primary proton energy spent for neutron
production for a proton energy of ~ 660 MeV is ~ 20 % according to our estimates of data [4]. It follows from [10] that for Еp ≈ 1
GeV it increases to 38,2%, reaching almost 46 % for 3,65 GeV. The extrapolation of this dependence to Еp = 10 GeV results in
the following estimate of this fraction:  60% (see [11] for details). Note that the growth of the ratio W/Еp is to a large extent
connected with the growth of meson production with increasing incident proton energy.
Еp,
GeV
< Е >,
MeV
Еkin,
MeV
Еkin / Еp, %
W,
MeV
W / Еp, %
0,994
8,82
213
21,3
382
38,2
2,0
11,6
513
25,6
822
41,1
3,65
13,7
1106
30,3
1670
45,6
Estimates power amplification coefficient for proton beam incident on
quasi-infinite target from metallic natural uranium.
Ер, GeV
Initial КPA
Equilibrium КPA
0,66
7,4
40
1,0
12,0
70
10,0
22,0
130
Gomel, July 22 - August 2, 2013
Gain power factor in the RNT - scheme
To a question about the expected energy gain G of
RNT-reactor
- Primary proton Ep= 10 GeV
heat loss
~ 34%
neutrons
~ 66%
equivalent
neutrons En= 6,6 GeV
Fission threshold 238U
~ 6600
of neutrons with En= 1 MeV
6600n0
(1 GeV= 1000 MeV)
0,2GeV(200MeV)=1320GeV
132 >> 5 > 3,3
Gomel, July 22 - August 2, 2013
G=1320 GeV / 10 GeV = 132
Physical basis of relativistic nuclear technology
The results of the estimates and the experiments show that in the scheme
NRT we have the opportunity to carry out with a hard neutron spectrum, having a
large enough component of the far abroad fission spectrum throughout its life
cycle.
Hard neutron spectrum in the volume of active zone RAW-system ensures
efficient treatment all threshold of actinides.
Moreover, for all treatment actinides there is shift of the elemental
composition of the fission fragments of nuclei in the isobaric chains in the
direction of short-lived or stable neutron-deficient nuclei. For example, instead of
generation a long-lived 129I, formed stable isotope 129Xe.
In addition, this spectrum provides an intensive course of reactions of type (n,
xn), which leads to a shift of the integral of the fission products in the direction of
short-lived neutron-deficient nuclei. For example, as a result of reactions (n, 2n),
(n, 3n) one of the most dangerous isotopes from the spent fuel - a long-lived 90Sr processed (transmuted) in the short-lived 89Sr or stable 88Sr.
Finally, the tightening of the neutron spectrum leads to an additional
suppression of the neutron capture reaction and significantly reduced operating
time more long-lived radioactive materials.
Gomel, July 22 - August 2, 2013
Existing facility of Nuclotron M
E&T
Gomel, July 22 - August 2, 2013
The main parameters of Nuclotron-M
Gomel, July 22 - August 2, 2013
Deuterons beam parameters.March 2012
Track density distribution by E= 1 GeV
March 2012
Itot=1.9·1013
Track density distribution by E= 8 GeV
March 2012
Itot=3.7·1012
Gomel, July 22 - August 2, 2013
The setup "Quinta" on the irradiation position
(December 2011 - March 2013)
Gomel, July 22 - August 2, 2013
Nuclotron session
in November-December 2012
Professor I. Zhuk
Professor A. Baldin
Gomel, July 22 - August 2, 2013
In the framework of the project the following tasks were
accomplished:

Construction of “Quinta” complex on the base of natural uranium.

Three systems of entering beam monitoring were developed –
•
Two systems are based on wire and proportional chambers with
wide
dynamic range and high spatial resolution.
•
Method of absolute monitoring is based on Al and Cu activation
taking
into consideration different measurement modes.

In collaboration with the Radium Institute of the RAS the method
of TPC detectors for neutron flow study in wide region of spectrum was
mastered.

The
method
of
planar
silicon
detectors
for
neutron
flow
measurement was elaborated.

Prerequisites for the transition to quasi infinite target “Buran” were
created.
Gomel, July 22 - August 2, 2013
General view of the beam monitoring systems
Since the aim of the experiments was to measure the absolute yield of the reactions under study it was required
to create secure interchangeable systems of beam intensity monitoring. Some of the held measurements required
knowledge of time structure of each pulse of accelerator and beam intensity variation during the session of
irradiation. Therefore, besides commonly used methods of off-line monitoring integral number of deuterons
incident on the target, it was necessary to develop on-line systems providing control of shape, intensity and time
dependence of accelerator pulses. Being proposed to operate at considerable variation of beam intensity such a
system should have wide dynamic range (105÷1012 ion/sec) and high (± 0,2 mm) precision of beam positioning on
the target.
For this purpose there were developed and successfully tested in experiments two independently operating
position-sensitive ionization chambers, operating in required dynamic range.
Gomel, July 22 - August 2, 2013
Results of the measurement of intensity, shape and position of beam
incident on the target with use of two monitoring systems. Relative
accuracy of ±5% in intensity was achieved for the systems of beam
diagnostics.
Gomel, July 22 - August 2, 2013
The main measurements of nuclearphysical parameters of set-up "Quinta"
 Measuring the hardness of the neutron
spectrum using of TFBC-detector
 The measurements of the neutron
spectrum using the activation technique
 The measurements of neutron leakage
from the set-up “Quinta” by passive silicon
detectors and scintillation detector DEMON
Gomel, July 22 - August 2, 2013
TFBC monitor of neutron or proton fluxes
The principle of detection
is based on an electrical
breakdown caused by a
fission
fragment
that
passes through a thin
silicon dioxide layer. The
breakdown is followed by
explosive vaporization of a
small part of the silicon
dioxide layer and the
metal electrode area. The
breakdowns
are
nonshorting, i.e., they leave
no permanent conducting
path
between
the
electrode and the silicon
base.
Gomel, July 22 - August 2, 2013
FISSION CROSS SECTIONS
Gomel, July 22 - August 2, 2013
EXPERIMENTAL SETUP AT VESUVIO
ELECTRONICS AND DATA ACQUISITION SYSTEM
Direct signals from an ntype TFBC at 50 Ohm
(upper line) and after
amplification by a fast
linear amplifier Phillips
Scientific 776 (lower line)
A direct signal from a ptype TFBC at 50 Ohm
(upper line) and the
corresponding NIM
signal after a
discriminator LeCroy
4608 (lower line)
Gomel, July 22 - August 2, 2013
Sensitivity of natU/209Bi ratio
to high energy end of neutron spectrum
Gomel, July 22 - August 2, 2013
Location TFBC and passive detectors along the perimeter of “Quinta”
Gomel, July 22 - August 2, 2013
Ratios of natU/209Bi (n,f)-reaction rates
( black – inside of TA QUINTA, red – on the surface)
Energy spectrum of leakage neutrons becomes more
“harder” with increase of deuteron energy !
Gomel, July 22 - August 2, 2013
Experimental data on the relationship natU (n,f) / 209Bi (n,f) (TPS) on the surface
of the lead assembly.
(The distances to positions 1-2 are measured from the beam axis, for positions
3-7 (and 11-12) along the Quinta - from the corners of the assembly, for
positions 8-10 from the beam axis)
Gomel, July 22 - August 2, 2013
The ratio of number of fission
natU(n.f)
/ 209Bi(n,f)
along the side of Quinta
(data for 0.66 GeV/A and 4 GeV/A is not displayed, but the trend - the same)
natU (nf) / 209Bi (n, f)
Group A. Smirnov (Radium Institute)
Neutron spectrum modified to fit experimental ratio
natU/209Bi (n,f)-reaction rates at QUINTA surface
Gomel, July 22 - August 2, 2013
Location of samples 6 GeV experiment
Gomel, July 22 - August 2, 2013
Yttrium Activaction detectors
Sample Material:
Reaction
(n,2n)
(n,3n)
(n,4n)
(n,5n)
(n,6n)
MeV
MeV
MeV
MeV
MeV
Threshold Energy
11,5
20,8
32,7
42,1
54,4
Gomel, July 22 - August 2, 2013
Y-89
Half Live Time
106,65d
79,8 h
14,74 h
2,68 h
39,5 m
Arrangement of the 89Y detectors on the detector
plates in the Quinta Assembly
Gomel, July 22 - August 2, 2013
Average neutron flux density per
deuteron in the third detector
plane (where maximum occurs)
and radius 4 cm for deuteron
beam energy 2.0, 4.0 and 6.0
GeV compared with the Monte
Carlo simulation using MCNPX
2.6 code. (March 2011)
Average neutron flux density per deuteron
[1/(cm2 MeV deuteron)
Average neutron flux densities per deuteron for the three
deuteron beams.
8x10
-4
6x10
-4
Third detector plane,
radial position 4cm.
Deuteron beam energy
Exper. 6 GeV
Exper. 4 GeV
Exper. 2 GeV
MCNPX, 6GeV
MCNPX, 4GeV
MCNPX, 2GeV
4x10-4
2x10
-4
0
Gomel, July 22 - August 2, 2013
20
40
60
Neutron energy [MeV]
80
100
56
N[59Co(n, 2α+4n)48V]/N[59Co(n, 2n)58Co]
48V / 58Co
1,35
1,30
1,25
1,20
1,15
1,10
1,05
1,00
0,95
0,90
0
2
4
6
8
10
Deuteron Energy
CSeff 15÷40 MeV
CSeff > 100 MeV
Eth = 10.6 MeV
47.6 MeV Threshold
Gomel, July 22 - August 2, 2013
Spatial distribution of density of (n,f), (n,γ) and (n,xn) reactions was studied using activation
of natural uranium foil (Ø 10 mm, 1 mm thick) placed on each detector plate at distances of R = 0;
4; 8 and 12 cm from the beam axis. Nf (R, Z) reaction numbers were defined according to the
average yield of 97Zr (5,42%), 131I (3,64%), 133I (6,39%), 143Ce (4,26%) fission fragments, while
Plutonium nucleus production NPu (R, Z) – according to the 239Np isotope yield in the chain:
238U(n,γ)239U
β- (23,45 min) →239Np β- (2,36 d) →239Pu
Distribution of density of 238 U(n,2n)237U β- (6,75 d) reactions was studied on the base of 237U
isotope activity.
Independent Nf (R, Z) values were measured with Solid-state Track Detectors (STD) having
“Quinta” target cross-cut
converters of natural uranium.
Y
beam window
150×150
channels for
mounting and
dismantling of
114
120
detector plates
Z
0
r 40
d
Section U-238
17
17
17
17
131
lead shield
262
393
524
655
700
900
Fig. 1
Geometry of the uranium
targets at the "Quinta"
1.6
1.6
Z =0
Nx10-5
Z =0
Nx10-5
The radial distribution of Nf (R,Z)
and NPu (R,Z) numbers (left and right
side of the figure) normalized to 1 kg
of uranium, 1 deuteron and 1 GeV
and measured in March 2012 at
deuteron energies of 1; 4 and 8 GeV.
1.4
1.4
1GeV M12
4 GeV M12
1.2
1.2
8 GeV M12
1.0
1.0
0.8
0.8
0.6
0.6
0.4
0.4
0.2
0.2
1 GeV M12
4 GeV M12
8 GeV M12
0.0
0.0
-10
Nx10
-5
10
30
50
9.0
70
90
110
130
150
Nx10-5
R, mm
Z =367.5
8.0
-10
5.0
10
30
50
70
90
110
130
150
R, mm
Z =367.5
4.5
4.0
7.0
3.5
6.0
5.0
1 GeV M12
4 GeV M12
3.0
1 GeV M12
4 GeV M12
8 GeV M12
2.5
8 GeV M12
4.0
2.0
3.0
1.5
2.0
1.0
1.0
0.5
0.0
0.0
Nx10
-5
1.8
-10
10
30
50
70
90
110
130
150
Nx10-5
R, mm
Z =612.5
1.6
1.4
-10
10
30
50
70
90
110
130
150
130
150
R, mm
Z =612.5
1.2
1.4
1.0
1.2
1 GeV M12
4 GeV M12
1.0
0.8
8 GeV M12
0.6
0.8
0.6
0.4
1GeV M12
4 GeV M12
0.4
0.2
8 GeV M12
0.2
0.0
0.0
-10
10
30
50
70
90
110
130
150
-10
10
a
30
50
70
90
110
R, mm
R, mm
b
c
Gomel, July 22 - August 2, 2013
The
two-dimensional
distributions of Nf (R,Z)
numbers (normalized to
1 cm3, 1 deuteron and 1
GeV) measured in March
2012 at energies of 1; 4
and 8 GeV. (a, b and c,
respectively).
Integral numbers of ( N totf ) fissions and 239Pu nuclei produced (
(per 1 deuteron and 1 GeV)
Ed = 2 GeV
tot
N Pu
Date
Ed = 1 GeV
03.11
12.11
03.12
11.8 ± 2.0
8.9 ±1.5
03.11
12.11
(10.6±0.5) ±1.1
Ed = 4 GeV
Ed = 6 GeV
Measuring method - ТТD
tot
Integral number of N f fissions
11 ±1.9
9.4 ±1.7
9.6 ±1.7
8.2 ±1.5
8.1 ±1.5
Activation method
tot
Integral number of N f fissions
(8.8±0.4) ±1.0
(8.8± 0.4) ±1.0
(8.3±0.4) ±0.9
(8.5± 0.4) ±1.0
03.12
(10.2±0.5) ±1.1
(9.6± 0.4) ±1.0
(9.4±0.5) ±1.0
(10.3±0.5)±1.1
(9.3±0.5)±1.0
12.12
(10.5±0.5)±1.1
03.11
Integral number of produced 239Pu nuclei
(7.0±0.3) ±0.8
(7.2±0.4) ±0.8
(6.9±0.3)±0.7
Ed = 8 GeV
10.0 ±1.7
9.2 ±1.6
12.11
(11.8±0.6)±1.2
(10.8±0.5)±1.1
03.12
(11.3±0.6)±1.2
(11.0±0.5)±1.1
(10.2±0.5)±1.1
(12.2±0.7)±1.3
(10.3±0.5)±1.1
12.12
(12.5±0.7)±1.3
Gomel, July 22 - August 2, 2013
)
Radiation hardness of silicon detectors
A. The detector leakage current increases linearly with hadrons fluence:
ΔΙ=αI⋅I ⋅ Φ ⋅ V
Φ − fluence, V − the detector bulk,
αI =(5±1) · 10 -17 А⋅см-1
for fast neutrons at T = +20⁰C (no self-annealing)
Possible solution:
• work at low temperature - (30-50)°C, detector leakage current
doubles it’s value every 8 degrees;
•Detectors module design required very good thermo contact
between Si-sensor and cooling plate for the excluding of the heating
and thermo break down /3/
Gomel, July 22 - August 2, 2013
Gomel, July 22 - August 2, 2013
Scheme for the neutron leakage measuring
(Top view. Detectors located at the beam axis)
Detector DEMON
Transmutation samples and
activation detectors
Sections of natU
«Quinta»
Window of beam entrance
detectors
(TFBC & PSD)
axis of the beam
180°
0°
13°
167°
1
156°
2
3
4
5
24°
lead assembly
131°
49°
113°
67°
90°
Gomel, July 22 - August 2, 2013
Neutron fluxes (in the 1 deuteron) on the "Quinta" surface in
various Ed
1.E-01
1.E-01
0,66 GeV/A
9.E-02
1 GeV/A
2 GeV/A
Flow n/(sm^2*d)
8.E-02
4 GeV/A
7.E-02
6.E-02
5.E-02
4.E-02
3.E-02
2.E-02
1.E-02
0.E+00
1
2
3
4
5
6
position number
7
8
9
10
Output of neutron leakage from the “Quinta" surface
Experiment - a group of Zamyatin
100%
9,4
8,8
8,8
11,3
79,6
81,6
82,3
80,5
11
9,6
8,9
8,2
80%
60%
40%
20%
0%
0,66
1
21
32
4
4
GeV/A
Gomel, July 22 - August 2, 2013
d
Measurement scheme with the “Demon”
Protection
Quinta
Detector Isomer
Pb
Instrumental spectra of detector Demon
Gomel, July 22 - August 2, 2013
Recovered spectra of neutrons
6
10
1 GeV/N <E> = 111,9 MeV <M> = 1
2 GeV/N <E> = 114,8 MeV <M> = 2,5
4 GeV/N <E> = 118,3 MeV <M> = 4,6
5
10
Neutron Flux
4
10
3
10
2
10
1
10
50
100
150
200
E,MeV
Gomel, July 22 - August 2, 2013
250
Results&Analysis
Comparison of neutron energy dependence of the weight ratios of 5-th
to (4+3-th) DN groups from 238U(n,f)-reaction and similar values
extracted from the DN time spectra measured in March 2011
4,8
4,8
238
R=Group4/Group5
System exp. data,
U+n
4,4
4,4
4,0
4,0
6 GeV
3,6
3,2
3,6
3,2
4 GeV
2,8
2,8
2 GeV
2,4
2,4
2,0
2,0
1,6
1,6
1,2
1,2
0,8
0,8
1
10
En, MeV
Gomel, July 22 - August 2, 2013
100
Final storage and
transmutation
Problem:
Safe disposal of highly radioactive waste for more than
100 000 years
Goal:
Minimisation of the long-lived waste
(plutonium and minor actinides, long-lived fission
fragments)
Transmutation into shorter-lived nuclides
Gomel, July 22 - August 2, 2013
Integrated reaction capture and fission reaction rate versus energy
in a FAST neutron energy spectrum
Gomel, July 22 - August 2, 2013
Minor actinides cross sections
Gomel, July 22 - August 2, 2013
Neutron capture – neutron induced fission
thermal spectrum
fast spectrum
Neutron capture is
dominating fission
in a thermal
spectrum
241Am(n,)
Fission is more
probable than
capture in a
fast spectrum.
241Am(n,f)
Gomel, July 22 - August 2, 2013
Ratio of neutron capture to fission
thermal spectrum
fast spectrum
Gomel, July 22 - August 2, 2013
Schematic drawings of the box with actinide samples
in the experimental window
Gomel, July 22 - August 2, 2013
Eight fission products were identified in the 237Np sample. Reaction
rates of all isotopes divided by the fission yield is presented in (a) and
the averaged ratio as a function of deuteron beam energy and the
same ratio related per GeV/A are presented in (b). Constant value of
fission events per GeV/A can be seen within uncertainties.
237
Np Fission
237
Np Reaction Rate Comparison
10
Np(n,f)FP
237
 R(n,f )  = 5.83(75) E-26
7
6
5
4
 R(n,f )  = 3.35(40) E-26
3
2
Identified radionuclide
--
135
I
138
Cs
142
La
133
I
97Z
r
97N
b
132
I
 R(n,f )  = 1.67(20) E-26
1
92
Sr
-1 -1
8
237
R-factor/Yield [1E26 · d-1A-1]
9
R-factor/Yield [1E26 · d A ]
7
1 GeV/ A
2 GeV/ A
4 GeV/ A
Np(n,f)FP per GeV/ A
6
5
4
3
2
1
0
1
2
3
4
Deuteron beam energy [GeV/ A]
Gomel, July 22 - August 2, 2013
The experimental results on the
measurement of fission quantity and
production of Plutonium and Uranium 237
Gomel, July 22 - August 2, 2013
Experimental results on reactions in natU (left); the same dependence
related per 1 GeV (right)
Reaction Rate Comparison
Deuteron beam energy [GeV/A]
Reaction Rate per GeV/A Comparison
Deuteron beam energy [GeV/A]
Gomel, July 22 - August 2, 2013
The reaction rates for all product nuclei increase with
energy of bombarding uranium assembly (target) deuterons
Ed = 2 ГэВ
Ed = 4 ГэВ
Ed = 8 ГэВ
Изотоп
<R>
<R>c
<R>
<R>c
<R>
<R>c
22Naa
1.37(27)E-28
-
3.47(69)E-28
-
2.34(47)E-27
-
22Nab
7.4(15)E-30
-
4.62(92)E-30
-
6.4(13)E-28
-
24Naa
1.77(8)E-28
-
3.30(40)E-28
-
1.55(19)E-27
-
24Nab
2.64(32)E-29
-
4.72(57)E-29
-
9.1(11)E-29
-
82Br
5.09(13)E-29
-
6.37(12)E-28
-
1.11(4)E-27
-
123I
1.68(8)E-29
1.26(16)E-29
3.46(38)E-29
3.30(51)E-29
-
-
124I
2.98(16)E-29
2.42(15)E-29
6.65(45)E-29
6.37(81)E-29
1.05(18)E-28
0.91(17)E-28
126I
9.43(29)E-29
6.42(28)E-29
2.40(5)E-28
2.19(9)E-28
4.46(20)E-28
3.92(20)E-28
130I
4.59(10)E-27
-
1.07(2)E-26
-
1.84(4)E-26
-
Gomel, July 22 - August 2, 2013
The main findings on the project
realization
The research of deeply subcritical electronuclear systems and features of its application to
energy production and radioactive waste transmutation
•
•
•
•
A significant value and increase in average energy of neutrons causing fission in limited
model of central area of Active zones, with increase in beam energy point out that
radioactive waste (RAW) may be used as reactor fuel on the base of nuclear relativistic
technologies (NRT-reactor) with cardinal reducing amount of its complicated radiochemical
recycling and burial of radioactive waste.
Proportion of increase in fission quantity and production of Plutonium to increase in beam
energy up to 8 GeV in conjunction with considerable increase in multiplicity and neutron
leakage average energy, as well as value of energy, taken out (neutron leakage ~ 90%),
bring out clearly the necessity to start carrying out of complex experiments at the
“Buran” setup.
The obtained results clearly prove the prospects of the NRT scheme. The final conclusions
on its “starting” quantitative characteristics, working out of ways of the NRT-scheme and
its elements application to nuclear and related industries will be possible only in course of
carrying out complex experiments at the “Buran” setup.
The “Buran” setup construction requires great financial, material and manpower costs,
which are incommensurable to those of the “E and T - RAW” project.
However the results obtained by now, its degree of reliability, repeatability totally justify these
costs.
Gomel, July 22 - August 2, 2013
The main tasks for the activities of the “E&T-SNF” project with the target setup BURAN for
2014÷2016
The experiments carried out during the 1st stage of the project in 2011-2013 on the base of
the target setup Quinta of the limited size allowed us to develop and test the main methods of
measuring and data processing. As result of analysis of the experimental results described above the
scientific and methodical programmes for measurements of the 2nd stage of the “E&T-SNF” project
with the quasi infinite target setup BURAN were refined. It also gave an opportunity to estimate real
terms and resources required for accomplishment of the programmes.
Consequently, the main tasks of the project aimed at experiments with the TS Buran for
2014-2016 are the following:
Study of spatial distribution of neutron fields and their energy spectra inside and on the surface of
the TS.
Defining spatial distribution of densities of uranium nuclei fission inside the TS.
Study of spatial distribution of 239Pu production and elimination (fission) dynamics and definition of
equilibrium concentration for the given core configuration.
Investigation of dependence of beam power amplification coefficient CAP on energy of bombarding
particles (protons and deuterons) in order to find its optimal value for the given type of particle.
Evaluation of velocity of recycling reactions of long-living isotopes composing RAW.
Obtaining full set of experimental data required for verification and modification of existing
theoretical models and transport codes, which can reliably describe and predict the properties of
accelerator driven systems.
Conditions required for “E&T-SNF” project implementation
The project scientific programme implementation is possible due to availability of the
unique target setup BURAN from depleted uranium (see Figures 29 and 30) at JINR. The uranium
target cased in solid steel 10 cm thick frame has a mass of about 21 tons, a diameter of 1.2 m and a
length of 1 m in relation to uranium.
As the TS BURAN was designed, produced and delivered to JINR for experiments at the
Synchrophasotron more than 20 years ago its adjustment to carrying out experiments at the
measurement hall in the Nuclotron F3 focus requires holding huge amount of designing and building
and assembly works. Besides, elaboration of the TS central zones of different type made from uranium
and lead is a complicated task.
Gomel, July 22 - August 2, 2013
General view of the target setup BURAN at the transport-fixing platform.
The scheme of longitudinal section of the TS BURAN
with the mounted central zone (left) and general view photo (right).
Integral characteristics of the target setup BURAN
bombarded with proton and deuteron beams calculated per 1 incident particle.
Protons
Deuterons
Ер(d), GeV
1
6
12
1
6
12
Total multiplicity
of neutrons
126
770
1450
125
794
1455
Reactions number
(n,γ)
70
440
826
70
452
837
Reactions number
(n,f)
16
100
183
15
100
183
CAP = Еtotal/Ep(d)
3.82
3.75
3.5
3.82
3.85
3.55
PROTONS
Ер(d), GeV
DEUTERONS
1
6
12
1
6
12
Fe-1
3.2
10
21
3.2
11
17
U-2
8
30
55
8.1
29
48
Fe-3
0.03
1
1.8
0.03
0.95
2.4
U-4
0.22
6
11
0.2
6
15
Fe-6
0.16
1.2
2
0.16
1.8
2.1
U-7
1
7.5
13
1.2
7.5
14
Total
3.34
13
24
3.34
13
22
Coordinates
Neutron leakage from the surface
of the target setup BURAN per 1
incident particle.
Gomel, July 22 - August 2, 2013
Thank you for
attention
Gomel, Belarus, July 22 - August 2, 2013