Hungary
Legal framework and waste classification
The fundamental law is the Act of 1996 on Atomic Energy declaring that the control and supervision
of the safe use of nuclear energy are Government’s tasks. These tasks are fulfilled through the
Hungarian Atomic Energy Authority (HAEA) and the responsible ministers. A divided regulatory
system is set up the Act and its executive orders:
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regulatory & licensing authority for nuclear facilities: HAEA
regulatory & licensing authority for RW management facilities: regionally competent
radiation health centres following the professional direction of the Office of the National
Chief Medical Officer (National Public Health and Medical Officer Services) under the
minister responsible for health
According to § 2, Paragraph 15 of the Atomic Act, any radioactive material, which will no longer be
used, and, due to its health physics properties, cannot be considered a common waste.
The 47/2003 (VIII.8.) Decree of the Minister of Health, Social and Family Affairs regulates among
others the classification of radioactive waste.
That type of radioactive waste is qualified as low and intermediate level radioactive waste in which the
heat production during the disposal could be neglected. Further,
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that low- and intermediate level radioactive waste is short-lived, in which the half-life of the
radionuclides is 30 years or less, and it contains long-lived alpha emitter radionuclides only is
limited concentration
that low- and intermediate level radioactive waste is long-lived, in which the half-life of the
radionuclides and/or the concentrations of the alpha emitter radionuclides exceed the limits
concerning short-lived radioactive waste.
That type of radioactive waste is high level waste whose heat production shall be considered during
the design and operation of storage and disposal.
Classification viewpoints for low and intermediate level radioactive wastes:
The classification of the radioactive waste into low and intermediate level classes shall be performed
based ont he activity-concentration and exemption activity-concentration (EAC) of the radioisotope
involved by Table 1.
Radioactive waste class
Low level
Activity concentration
(Bq/g)
1 EAC – 103 EAC
Intermediate level
103 EAC
If the radioactive waste contains more types of radioisotopes, then the classification shall be performed
accordingly as follows:
Radioactive waste class
Low level
Activity concentration ratio
ACi
 EAC
i
i
 103
Intermediate level
ACi
 EAC
i
 103
i
where ACi is the activity-concentration of the i radioisotope existing in the radioactive waste, while
the EACi is the exemption activity-concentration of the ith radioisotope.
Disposal facilities
Currently, two waste disposal facilities for low and intermediate waste (LILW) are in operation in
Hungary.
The very first disposal facility was a near surface disposal facility. It was put into operation in 1960 in
Solymár. It operated until 1976, when a newly designed near surface repository started its operation in
Püspökszilágy.
The Radioactive Waste Treatment and
Disposal Facility (RWTDF) has a bigger
capacity and adopted the radioactive waste
from Solymár and from all sources in the state.
The facility was technically implemented by
the construction of near surface pools and
storage tubes (wells).
The National Radioactive Waste Repository
(NRWR) is the other active facility, which is
near Bátaapáti village. The NRWR is designed
to accommodate all operational and
decommissioning radioactive waste arising
from Paks NPP.
Püspökszilágy Radioactive Waste Treatment and Disposal Facility
The Hungarian Radioactive Waste Treatment and Disposal Facility (RWTDF) located in the ridge of a
hill near Püspökszilágy village at an altitude of 200 – 250 m above sea level. The repository was
completed and commissioned in 1976, for the disposal of radioactive waste from health care, research,
educational and industrial applications. The repository also received low level solid waste from Paks
Nuclear Power Plant from 1983 till 1996.
The facility is a typical shallow land, near surface engineered type disposal unit. It is composed of
(1) concrete trenches („A” and „C” type vaults) for disposal and shallow wells for storage
purposes for LIL solid RW and spent sealed radioactive sources;
(2) „B” and „D” types of wells are mainly reserved for the storage of highly active
sources.
The „A – type” vault system contains 60 vaults each of 70 m3 and 6 vaults each of 140 m3.
Some drums in the vaults have been backfilled with cementitious material, other drums are not yet
backfilled. The „C-type” storage system consists of 8 vaults, each of 1,5 m3, sunk into the ground.
The vaults and wells are located above the water table in relatively impermeable rock. The inner walls
of the vaults are covered by a waterproof layer. There are 16 wells of „B-type” with a diameter of 40
mm, and 16 wells with diameters of 100 mm. The wells are made from stainless steel, they are 6 m
deep, located inside a monolithic concrete structure. The „D-type” storage unit consists of four carbonsteel wells, each one is 6 m deep and has a diameter of 200 mm. They can be locked and are provided
with a protective cap. These wells were utilized for storing spent radiation sources with half-life of
greater than 5 years.
The total capacity of concrete trenches is 5040 m³ which was extended from 3500 m3 in order to
accommodate a portion of the low-level solid radioactive waste from the Paks NPP. Wastes from the
Paks NPP occupy about 2500 m3 of the capacity of the site. The free disposal capacity of the site had
declined, which is sufficient to accommodate the annual amount of approximately 20 m3 stemming
from non-power generation activities for the coming years.
The transport of radioactive waste from waste generators to the site and on-site is organized by
radioactive waste management company its own responsibility, using its own workforce and
equipment e.g. transport vehicle, containers. If treatment is required prior to disposal, then the waste is
temporarily stored. Treatment may be solidification, sponging up of liquid by absorbing material or by
repackaging, it depends on the waste type.
Originally the record keeping system was based on paper documents, but during the 1980s this system
was replaced by a computerized database. The new waste inventory record keeping system was
designed in accordance with international recommendations (IAEA TECDOC 1222).
The site is guarded by well-equipped security guards, applying up-to-date security systems. The access
control system ensures that only licensed persons and shipments have access to the site and can stay
there.
The radiation protection control begins already at the waste producers when receiving the waste.
Surface dose rate and contamination of the packages are regularly measured. The transport vehicles
are subject to radioactive contamination and exposure control. The exposure of personnel is measured
by two different types of personal dosimeter.
The monitoring system was planned and installed to provide information and data about the
radiological conditions of the repository and its environment. Meteorological data are collected by a
special station. The water collection system is designed to collect run-off and is routed to two large
basins. The radioactivity of the collected water is sampled and monitored before being discharged via
a drainage ditch to a local stream. Soil-, flora- and fauna samples are taken from the site as well as
from the 20 km vicinity of the repository. Analysis of the fish samples taken from a nearby pond is
also part of the environmental monitoring programme. Radioactivity of flesh, bones and the pluck of
sheep, and goats grazing in the vicinity of the site is regularly measured.
The result of the safety assessments, at the same time, unambiguously indicated that certain spent
radiation sources may pose a risk in the distant future, after the closure of the repository in case of
human intrusion. Therefore, with the aim of enhancing the long term safety of the repository, a multiyear programme was launched in the framework of which the „critical” waste types are segregated
from the recovered waste and then the rest are – as far as possible – compacted before redisposal in the
vaults. By doing this, the repository can continue to accommodate the institutional radioactive waste
from all over the country.
Short history of RWTDF
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1976 - Licencing of the Radioactive Waste Treatment and Disposal Facility in Püspökszilágy
for institutional waste.
2002 – 2005 Safety upgrading program (Phase I) based on previous safety assessments
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2007 – 2009 New activities began in the framework of the second phase of the safety
enhancement program. Plans were prepared and approved for opening 4 vaults (each of 70m3
containing mainly historical waste) and for retrieving, selection, reconditioning and
repackaging waste.
2013 – Preparations to continue the safety enhancement programme and a physical protection
programme with US-DOE.
National Radioactive Waste Repository (NRWR)
The NRWR is operated in the region of Bátaapáti as a facility for final disposal of low- and
intermediate level wastes from nuclear power plant. The repository is an underground repository in
granite host rock. The disposal is done in disposal chambers using concrete containers.
Two parallel tunnels, each with length of 1700
m and an inclination of 10 %, were excavated
parallel, at distance of 25 m from each other
between the planned base point and the surface
starting point to allow the completion of the
underground investigation work. These tunnels
have been interconnected thus providing for
the required through ventilation and two
separate escape routes for the case of accident
or fire. The whole drifted tunnel length is 5500
meters.
The radioactive waste from the operation of the nuclear power plant is ad-interim stored in the power
plant site, up to their transfer into disposal facility. The solid wastes are loaded, in compacted form,
into 200 l drums. The liquid waste are solidified in the power plant prior to their transfer into disposal
facility. The waste packages are transported by a special purpose vehicle from the Paks NPP to the
disposal site. The vehicle is received in the central building of the disposal site. Following an
inspection, the vehicle moves in to the process hall in the controlled zone where, after the completion
of an additional inspection, the transport frames are lifted off and placed by a crane into the storage
room. Control tests and the preparation of the waste for underground storage are carried out in the
process hall, which is capable of accommodating 3000 drums. The disposal would be done in the
disposal chambers using concrete containers. It was planned to put nine 200 l drums into one container.
For cemented radioactive liquid waste, 400 l drums would be used and in this case five drums would
be put into one container. In order to reduce the volume of waste packages, npp had decided to
overview of the waste cementation technology and a new concept of solidification began to form:
instead of cementing radioactive liquid into drums, radioactive grout is going to be used to fill up void
in the disposal containers. The new, smaller size container is planned to have reinforced steel walls.
The new waste package requires a new way of disposal as well. The planned change in the disposal
concept is to build a high quality concrete vault in the disposal chamber and stack steel containers in
them. The vaults are planned to have separate blocks, which could play two roles: reinforce the walls
of the vault and make phased backfilling possible. Phased backfilling possible of the vaults enables the
operator to create high quality engineer barrier near the waste with close control and without radical
improvement of the „off-the-shelf” technologies. The environmental monitoring system is composed
of three parts as follows: the geological and hydro-geological, radiological and conventional
environmental monitoring.
The originally planned system of the NRWR on the left and new disposal concept on the right.
Short history of NRWR
 1993 - A National Program was launched with the aim of finding a solution for the final
disposal of LLW/ILW of the plant.
 1996 - Decision to investigate the Bátaapáti (Üveghuta) site for a subsurface repository in
granite
 1997-1998 - Exploration of the suitability of the potential site Bátaapáti (Üveghuta).
 1999 - IAEA WATRP Mission confirms the results of the investigation and recommends
further exploration of Bátaapáti (Üveghuta).
 2000 - Collection of existing data and preparation of a preliminary safety assessment to
establish further investigation in Bátaapáti (Üveghuta).
 2001-2003 - Detailed geological and hydrogeological survey from the surface as well as safety
assessment of Bátaapáti (Üveghuta) site. The geological authority stated that the site fulfils all
the requirements formulated in the relevant decree: thus, from the geological point of view it
is suitable for the disposal of LILW.
 2004-2006 - The programme of further investigations of Bátaapáti (Üveghuta) site
(construction of two parallel inclined shafts in order to determine the exact location of the
repository and its safety zone) was approved by the competent minister in December 2004.
 2005 - After the strongly supportive result of a local referendum held in the village of
Bátaapáti, the Hungarian Parliament expressed its approval in principal for the construction of
the repository
 2006 - The Governmental Decree 257/2006. (XII.15.) declared that the Bátaapáti LILW
repository project is an issue of preferential importance and as such it enjoys certain priorities
in licensing and legal procedures.
The first part of the environmental licensing procedure was accomplished in January 2006
when the regionally competent authority accepted the Preliminary Environmental Impact
Study giving green light to the second part of the procedure: the compilation of the
Environmental Impact Assessment.
In parallel with on-going underground geological investigations in Bátaapáti the following
additional activities started in 2006:
o preliminary activities (landscaping, planning etc.) for aboveground infrastructures of
the future LILW repository;
o preparation of licensing documentations of the future LILW repository.
 2007 - Construction licensing of the Bátaapáti LILW repository started on 8 November 2007
when the necessary documentation based on safety assessment (Pre- construction Safety
Assessment) was handed to the competent authority.
The competent authority issued the Environmental License for the Bátaapáti LILW repository
which entered into legal force on 17 October 2007.
 2008 - On the basis of the pre-construction safety assessment the authority issued the
construction licence of the Bátaapáti LILW repository in May 2008. The operation licence for
the surface part entered into force in October, allowing for the temporary storage in the
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technology building. The name of the new facility in Bátaapáti is National Radioactive Waste
Repository.
2012 - The underground part of the repository was carried out.
2012 (Sept.) - Operation licence for the underground part.
2012 (Dec.) - The first concrete container is disposed in the first chamber.