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)

17

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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