Experimental research of
constructional material
radiation heat-up at IGR
Reactor
A.T. Izbaskhanova (ASE IAE RSE NNC RK, Kurchatov,
Safety issue
Safety issue
Tightening of safety regulations
of designing and existing NPP is
the main issue of the up-date
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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.
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)
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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
.IGR Reactor
IGR Reactor
IGR Reactor is intended to
produce neutron flux of
high density
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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,
IGR Reactor characteristic
Core temperature
Delay mechanism
Coolant
Core height
Horizontal core section
1400 К
Graphite
Water
IGR Reactor: operating modes
Uncontrolled mode
IGR Reactor: operating modes
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.
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
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
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
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
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