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Experimental research of constructional material radiation heat-up at IGR reactor

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(1)

Experimental research of

constructional material

radiation heat-up at IGR

Reactor

A.T. Izbaskhanova (ASE IAE RSE NNC RK, Kurchatov,

(2)

Safety issue

Safety issue

Tightening of safety regulations

of designing and existing NPP is

the main issue of the up-date

(3)

3

IGR Reactor

IGR Reactor

The unique Complex of research reactors IGR

(CRR IGR) located at the area of the former

Semipalatinsk Test Site is being operated in the

Institute of Atomic Energy NNC RK (IAE NNC

RK) over fifty years. TREAT Reactor (USA, ANL,

Argon National Laboratory, 1958) was a

prototype of IGR Reactor.

(4)
(5)
(6)

IGR Reactor

IGR Reactor

Physical start-up – June, 1960

Power start-up – August, 1961

Reactor was updated in 1967 including

increase of U-235 mass in the core

(from

7,46 kg to 9,0 kg) and increasing of central

experimental channel diameter (from 180mm

to 290mm)

(7)

7

IGR Reactor

IGR Reactor

Pulse reactor on thermal neutrons with

homogeneous uranium-graphite core

operates in programmed power impulse

mode and by a principle of shutdown of

any impulse

.

(8)

IGR Reactor

IGR Reactor

IGR Reactor is intended to

produce neutron flux of

high density

(9)

9

IGR Reactor

IGR Reactor

Among the same reactors IGR

possesses the highest thermal neutron

fluence (3,7*1016 сm-2 ) and power of

-radiation dose - 4,78*107 rad per one

start-up in the experimental cavity in

the central part of reactor (dia - 228 mm,

(10)
(11)
(12)

IGR Reactor characteristic

Core temperature

Delay mechanism

Coolant

Core height

Horizontal core section

1400 К

Graphite

Water

(13)

IGR Reactor: operating modes

Uncontrolled mode

(14)

IGR Reactor: operating modes

(15)

IGR Reactor

Successful IGR operation of many years

proved its uniqueness; IGR is optimal for

fast process study being characterized

structural material behavior of many

reactor facilities postulate accidents

including:

LOCA – loss-of-coolant accident

PIA – reactivity, power-burst accidents;

PCM – power and cooling unbalance,

including emergency protection failure

accompanying with fuel destruction.

(16)

Experimental researches being

performed at IGR Reactor

Tasks, being realized at IGR Reactor cover the following areas:

reactor physics

reactor technology

fuel and reactor material testing under critical

heat conditions

radiation staff resistance

core element behavior from graphite units

with homogeneous nuclear fuel under high temperatures

(17)

Issues of radiation heat-up

In 2000 experts from IAE NNC RK, RFNC VNIITPh, NIKIET, RSC “Kurchatovskiy

Institute” started with

calculated-experimental researches of structural material radiation heat-up as affected of

neutron and gamma radiation. In 2002, basing on CRR IGR first experiments on

the measuring of radiation heat-up temperature with IGR irradiation were

(18)

Issues of radiation heat-up

Basing on IGR Reactor series of

experiments on study of radiation

heat-up of some structure materials with

following failure is in progress today;

experiments on study of IGR fuel block

behavior within beyond-of-design

accidents under neutron neat-up up to

high temperature, right up to

(19)

Experimental devices

1 – vessel –ready-assembled power cover, 2 – lid with experimental button, 3 –sensor connectors, 4 –lower adapter, 5 –upper adapter, 6 – adapter, 7 – thermal connector fitting, 8 – control rod, 9 –disc, 10 – quartz location plate, 11 – sample of investigated material, 12 – check screw, 13 – thermocouples,

14 –shell, 15 – pipe

Experimental devices РР-1 and РР-2 are intended for in-pile experiments of radiation heat-up of structure materials by the

irradiation of IGR Reactor; ED PP-2 has a sell made from 12Х18Н10Т stainless steel. ED allow to illuminate up to 16 samples

(20)
(21)

Prospects of IGR reactor utilization

Now CRR IGR is one of the few reactors in the world where carrying out of the most

representative researches of behavior of fuel, materials and reactor elements is possible within simulation of transient and

emergency modes. Uniqueness of the IGR experimental base, received results saved up

for 50 years of work experience is aroused quite clear interest of Experts from various

(22)

Conclusion

Research results performed at IGR

Reactor allow enhancing reliability

and safety of the atomic power

stations. In fact, nuclear

establishment safety substantiation

is a basic condition for successful

realization of coming projects

(23)

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