proposals for multilateral experimental research...
TRANSCRIPT
PROPOSALS FOR MULTILATERAL EXPERIMENTAL
RESEARCH PROGRAM USING MBIR CAPABILITIES.
V.A.Eliseev, A.V. Gulevich, D.A. Klinov (JSC “SSC RF – IPPE”)
14 November 2019
Dimitrovgrad, RF
2
TWO-COMPONENT NUCLEAR POWER
• Solving the problems of SNF accumulation in the
world;
• Increasing in tens of times the efficiency of
natural uranium;
• Minimization of the volume and mass of
radioactive waste with the reduction of the period
of their radioactivity decay due to minor actinides
burning in fast neutron reactors.
Two-component nuclear power is synergistic coexistence of the
fleet of thermal and fast reactors
Thermal reactor fleet Fast reactor fleet
Closure of nuclear fuel cycle requires effective solutions
on the improvement of SNF reprocessing technologies and the incorporation
of minor actinides in the fuel composition of fast NP
Nuclear power and closed NFC
Two-component nuclear power with thermal and fast reactors
Combined closed nuclear fuel cycle
Development of the NFC technologies. Practical implementation at
the demonstration and pilot application stages
Economic competitiveness of fast reactors as compared with
thermal ones
Experimental program will have to be carried out at the MBIR fast
research reactor built in Russia to replace the BOR-60 research
reactor.
Characteristics of fast neutron RRs
4
Parameter FBTR (India) Joyo (Japan) CEFR (China) MBIR (Russia)
Status Operates at 50% of
design power
Temporarily shut
down
In operation Under
construction
Fuel Design: 65 FAs with
MOX fuel
MOX: with Pu content
of 16 % (23 FAs) and
21 % (59 FAs)
MOX fuel,
enrichment in235U - 18 %
Vibro-MOX with
Pu content of up
to 38.8%
Commissioning 1985 1977 2010 2025
W(th), declared /actual,
MW
40/20.3 140/ - 65/- 150/-
Fmax (total/fast), 1/m2·s 3.15·1015/-
(with W=40 MW)
5.7·1015 / 4.0·1015 3.7·1015 / 5.3·1015/3.7·1015
Radiation damage,
dpa/year
Up to 40
Operating hours per
year
1900 h/year
Design: 4200 h/yearCycle duration 60
days Declared: 4872
h/year
- Cycle duration
100 days
5700
Design life, years 30 (2015) 30 (2007) 40 (2050) 50 (2075)
Layout of MBIR reactor core
5
94 FAs,
3 LChs,
3 cells for instrumented experimental assemblies or
EChs,
13 cells for non-instrumented assemblies,
8 cells with CPS control members.
- FAs
-CPS control rods
- ED simulator
- SS assembly- SS assembly in place of LCh
- SFAs
- Package of in-pile storage
assemblies
Reactor core characteristic and parameter BOC MOC EOC
Maximum core neutron flux, 1015 cm-2∙s-1 5.08(0.706) 5.20(0.708) 5.28(0.701)
NF in CLCh at the core center level / fuel height
average, 1015cm2∙s-1
4.78(0.645)
4.17(0.628)
4.85(0.637)
4.22(0.622)
4.88(0.631)
4.26(0.616)
NF in LCh1 at the core center level / fuel height
average, 1015 cm-2∙s-1
1.94(0.543)
1.71(0.527)
2.01(0.539)
1.77(0.523)
2.07(0.533)
1.82(0.519)
NF in LCh2 at the core center level / fuel height
average, 1015 cm-2∙s-1
1.26(0.431)
1.13(0.418)
1.27(0.426)
1.13(0.415)
1.27(0.424)
1.14(0.413)
NF in ECh1 at the core center level / fuel height
average, 1015 cm-2∙s-1
3.95(0.687)
3.44(0.673)
3.93(0.682)
3.42(0.668)
3.90(0.678)
3.40(0.664)
NF in ECh2 at the core center level / fuel height
average, 1015 cm-2∙s-1
3.62(0.684)
3.14(0.670)
3.59(0.679)
3.12(0.665)
3.55(0.675)
3.09(0.661)
NF in ECh3 at the core center level / fuel height
average, 1015 cm-2∙s-1
3.06(0.681)
2.67(0.666)
3.16(0.675)
2.74(0.661)
3.23(0.669)
2.81(0.656)
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EXPERIMENTAL CAPABILITIES OF MBIR
Experimental devices Location Number Size Neutron flux in the volume,
x1015 cm-2·s-1
Cells for non-
instrumented material
test assemblies and
isotope production
assemblies
Reactor core 14 One cell:
Width across
flats – 72 mm
Maximum: 4.9
Average for all cells for the core
center: 3.6
Cells for non-
instrumented material
test assemblies and
isotope production
assemblies
Side screen Limited by
SS size
One cell:
Width across
flats – 72 mm
Maximum: 2.6
Average for all cells for the core
center: 1.0
Experimental channels Reactor core 3 One cell:
Width across
flats – 72 mm
Max./aver. in EC1: 3.9 / 3.3
Max./aver. in EC2: 4.0 / 3.5
Max./aver. In EC3: 3.7 / 3.2
Loop channels Reactor core
center
Side screen
1
2
In place of 7
core cells of
Ø100 mm
Max./aver. in CLC: 5.0 / 4.4
Max./aver. in LC1: 2.1 / 1.8
Max./aver. in LC2: 1.8 / 1.6
Neutron spectra in CLC, LC1 and LC2
(at the fuel portion level)
Neutron spectra in EC1, internally
localized МTAs and
peripherally localized MTAs (at
the fuel portion level)
Neutron spectra in SS, SS interior and SS
periphery (at the fuel portion level)
Neutron spectra
18
OVERALL VIEW OF MBIR REACTOR
1 – handling mechanism,
2 – CPS actuators;
3– rotary plugs;
4– plug rotation devices;
5 – loop channel;
6– VEC;
7– primary pipelines;
8 – HEC;
9 – vessel and safeguard case;
10 – FA;
11 – radial reflector
1
2
3
5
4
6
7
8
9
10
11
8
MAJOR SPECIFICATIONS OF MBIR REACTOR FACILITY
9
Parameter Value
Thermal power, MW ~ 150
Electrical power, MW ~ 40
Maximum neutron flux, 1/ cm2·s ~ 5,3·1015
Regular fuel Vibro-MOX
Experimental fuel Innovative fuel types, fuel with МА
Reactor core height, mm 550
Maximum linear fuel rating,W/cm 470
Maximum fluence per year, 1/cm2 ~ 1·1023 (up to 45 dpa)
Life time, year 50
Number of independent loops with different coolants Up to 5 (3 loop channels)
Total number of experimental assemblies and irradiation devices for
isotope production
Up to 14 (core)
Not limited (side screen)
Number of experimental channels Up to 3 (core)
Number of horizontal experimental channels (ø 200 mm) Up to 3 (outside the reactor tank)
Number of vertical experimental channels (ø 350 mm and 50 mm) Up to 9 (outside the reactor tank)
REQUIREMENTS TO LOOP CHANNELS
Parameter LCh-Na LCh-Pb LCh-Pb-Bi LCh-Gas
(He)
LCh-Salt
Coolant Sodium Lead Lead-
bismuth
alloy
Gas (high
purity
helium)
Metal
fluorides
melt
Neutron fluence in
LCh,
cm-2·s-1
≥ 3·1015 2·1015 (2÷3)·1015 (0.4÷1)·1015 Up to
3.5·1015
Power, MW Up to 1.0 ≥ 0.3 Up to 0.8 Up to 0.15 Up to 0.15
External diameter,
mm
≥ 190 ≥ 190 ≥ 190 ≥ 130 ≥ 150
Fuel length MBIR
core
height
MBIR
core
height
MBIR core
height
Side
reflector
height
MBIR core
height
Тin/Тout of working
fluid, 0С
320/550 Up to
350/
up to
750
Up to 350/
up to
500
≥ 950 750/ 800
10
Irradiation capabilities at the initial stage of operation
• Irradiation volume of the MBIR reactor for optimal variant of initial
configuration is 21 cells (2.28 litters of each), litters 48
• Average damaging dose rate per micro-campaign (100 eff. days), dpa 10.5
• The reactor availability factor 0.65
• Average damaging dose rate for irradiation cell, dpa/year 25
• Maximal damaging dose rate for central cells, dpa/year 38.5
• Total damaging dose rate of MBIR, dpa*l/year 1200
• Similar characteristic in the BOR-60 reactor, dpa*l/year 300
PROPOSALS OF MUTUAL INTEREST FOR
INTERNATIONAL COLLABORATION
• Irradiation capabilities of fuel rod samples,
including fuel with minor actinides
• Behavior under transient conditions, including
abnormal ones (loss of flow, transient of power,
control rod withdrawal, …)
• Experiments for verification of computer codes
• Nuclear medicine
• Isotope production
• Fundamental research (ultracold neutrons and
etc.)
12
Basic Directions of Russian R&D
Key directions of research to be done at MBIR, aimed at justifying
the fuel cycle closure technologies in the two-component nuclear
power:
- material science studies
- studies on new fuel compositions
- transmutation of minor actinides
- testing the reactor equipment in transient and
emergency processes
- verification of computer codes
14
Structural Materials
Scope of Work Objective Projects
High-dose irradiation (160÷200 dpa) in
dismountable facilities of new advanced
materials (ferritic-martensitic steels
operational at 650÷700 °C, austenitic steels,
ODS steels) to study mechanical properties,
swelling and irradiation creep.
• High burnup of fast reactor fuel
(15÷20% of h.a.)
• Providing the fuel lifetime to
5÷10 years, increasing the capacity
factor.
• 50÷60 years lifetime of irremovable
core components.
BN-1200
BREST
ASTRID
ALFRED
CFR-600
PGSFA
High-dose irradiation (120÷180 dpa) of special
heat-resisting materials operational at
1000÷1100 °C
• H2 production and other advanced
non-electric power technologies.GFR
ALLEGRO
In-core studies of advanced low-absorbing
and corrosion-resistant materials, including
those based on silicon carbide and advanced
ceramics operational at the pressures of
25÷30 MPa and coolant temperatures of 570÷580 °C
• To justify the optimal material for
SCWR reactor fuel cladding.SCWR
Studies of radiation-resistant, heat-resistant
and corrosion-resistant (in relation to lithium
coolant) materials.
• To select and justify the optimal
variant of structural materials for the
thermonuclear reactor lithium loop,
first wall and blanket.
• ITER
• DEMO
Fuel can be irradiated in the MBIR reactor in order to verify
calculations of the isotopic composition of the experimental fuel
(MOX, MOX + MA, mixed nitride U-Pu) irradiated in MBIR.
Research on modification of isotopic composition, with relatively
highly enriched uranium fuel at the stage of the fast reactor start-
up and subsequent transition to uranium-plutonium fuel (option
for BREST-type reactors with dense nitride uranium fuel).
CNFC OF TWO-COMPONENT NUCLEAR POWER
FRTR
Fuel studies
MOX fuel for BN-800 and BN-1200 reactors in order to
increase the burnup to 17 - 20% h.a.
Dense nitride uranium-plutonium fuel for BREST-type
reactor (burnup to 8 – 12%h.a.)
Metal uranium-plutonium fuel
MOX/nitride fuel + MA
Thorium-based fuel
Testing the reactor equipment in transient and emergency reactor processes
Behavior of FEs under transient conditions, including
abnormal ones (loss of flow, transient of power, control rod
withdrawal, …) fuel destruction and meltdown!
Studies of the systems of passive protection of the
reactor
Studies of the reactor equipment under non-stationary
conditions
CONFIRMATION OF FEASIBILITY AND EFFECTIVENESS OF
THE INNOVATIVE ENGINEERING SOLUTIONS
- Heat exchanging modules of various steam generators (once-
through or inverse)
- «Sodium-sodium» heat exchangers with state-of-the-art
functional elements
- Electromagnetic and electromechanical pumps differing in
design with implemented innovative engineering
- Life tests of sodium monitoring instrumentation
- Different systems of sodium coolant purification
- Advanced acoustic systems for early detection of emergency
processes which can include local boiling or boiling of sodium
MBIR experimental capabilities for verification of computer codes
Verification of integral computer codes (COREMELT, SOKRAT-BN,
EVKLID, SIMMER, CATHARE, TRACE, etc.)
Experimental data on thermohydraulic processes in the upper
plenum under transient conditions (loop disconnection, etc.)
for verification of thermohydraulic codes (2D- and 3D-
versions of the COREMELT thermohydraulic module).
MBIR experiments with irradiation of the advanced fuel types
for verification of fuel codes (DRAKON, BERKUT, etc.)
High-tech experiments on fuel behavior under transient
conditions, including the accidents Total-Instantaneous-Blockage
(TIB), Loss-of-Flow (LOF) и Transient-of-Power (TOP), similar to
the FFTF experiments in the frame of TREAT program.
THANK YOU FOR ATTENTION !
https://www.oecd-
nea.org/download/science/workshops/fides
/documents/20190412IRCMBIRmultilateral
RDprogram.pdf
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