IAEA/USA Interregional course on
Preparations to Ship Spent Nuclear Fuel (1997)
STATUS OF RESEARCH REACTOR SPENT FUEL
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Dr. Iain G. Ritchie
Nuclear Fuel Cycle and Materials Section
Division of Nuclear Power and the Fuel Cycle
International Atomic Energy Agency
P. O. Box 100
A-1400 Vienna, Austria
IAEA/USA Interregional Training Course
Technical and Administrative Preparations Required for Shipment of Research Reactor Spent Fuel to its Country of Origin
13-24 January 1997
STATUS OF RESEARCH REACTOR SPENT FUEL WORLD-WIDE:-
I. G. RITCHIE
Nuclear Materials and Fuel Cycle Technology Section
Division of Nuclear Fuel Cycle and Waste Management
International Atomic Energy Agency
Wagramer Strasse 5, P. O. Box 100
A-1400 Vienna, Austria
Results complied in the research reactor spent fuel database are used to assess
the status of research reactor spent fuel world-wide. Fuel assemblies, their
types, enrichment, origin of enrichment and geological distribution among the
industrialised and developed countries of the world are discussed. Fuel management
practices in wet and dry storage facilities and the concerns of reactor operators
about long-term storage of their spent fuel are presented and some of the activities
carried out by the International Atomic Energy Agency to address the issues
associated with research reactor spent fuel are outlined.
Activities in the area of management, interim storage and ultimate disposal
of spent nuclear fuel from research and test reactors are dominated at the present
time by two important programmes. The first is the Reduced Enrichment for Research
and Test Reactors (RERTR) programme, and the second is the take-back of spent
research reactor fuel by the country where it was originally enriched. In the
minds of most research reactor operators, especially those with fuel enriched
in the United States, these two programmes are closely linked because a spent
fuel take-back programme is the only tangible benefit to be gained from the
conversion of their reactor cores from burning highly enriched uranium (HEU)
to low enriched uranium (LEU), other than the altruistic goal of non-proliferation.
The RERTR programme has already limited and will, if it becomes global, eventually
eliminate all trade in HEU for research reactors to the ultimate benefit of
A the time of writing, there is only one take-back programme of spent research
reactor fuel by a supplier country in operation. On 13 May 1996 the Record of
Decision on a Proposed Nuclear Weapons Non-proliferation Policy Concerning Foreign
Research Reactor Spent Nuclear Fuel was published by the United States Department
of Energy (DOE). The implementation of this Policy has already begun with shipments
of spent fuel from research reactors in Europe and South America to DOE's Savannah
River Site in the latter half of 1996. It is hoped that other supplier countries
and partners in RERTR will follow suit and implement their own take-back programmes
for foreign research reactor spent fuel.
Although the IAEA has been involved with and has fully supported RERTR since
its inception through its Department of Research and Isotopes, it was not until
1993 that the Nuclear Fuel Cycle and Waste Management Division extended the
scope of its spent fuel management programme to include programmes which focused
specifically on spent fuels from research and test reactors. These activities
cover the collection, analysis and dissemination of information on storage,
management and related experience with spent fuels, formulation of norms and
provision of technical assistance to developing Member States. A number of concerns
were immediately apparent at the beginning of 1993. Many research reactors were
in a crisis situation or rapidly approaching a crisis situation and in every
case, this was due to spent fuel storage and management problems and the constraints
of national laws. It was clear that the capacity for spent fuel storage had
been reached or was close to the limit at many research reactors and there were
concerns from a materials' science point of view about ageing materials in ageing
storage facilities. The IAEA's activities in this area have been formulated
to address these concerns, but the first step was to obtain an overall picture
of spent fuel management and storage world-wide. This has been attempted by
the circulation to research reactor operators of questionnaires specifically
designed to form the input to the Research Reactor Spent Fuel Database (RRSFDB).
Construction and maintenance of this database is an ongoing activity and this
report provides a snapshot at the time of writing of the salient information
gleaned from the infant RRSFDB supplemented by information from the more established
Research Reactor Database (RRDB).
2. General Overview
Most of the information presented in this section is taken from the RRDB, specifically
from the IAEA publication "Nuclear Research Reactors in the World"
December 1995 Edition . The RRDB was first published in 1989  and has
been maintained ever since. As of December 1995 there was information on 588
reactors stored in the RRDB. Of these, 283 were operational, 12 under construction,
7 planned, 285 shut-down and 1 for which the information was not completely
The evolution of the number of countries with at least one research reactor
is shown in Figure 1. This distribution peaked for developing countries in 1985
but remained almost constant for industrialised countries from 1965 to the present.
The IAEA divides the world into seven regions and those countries with at least
one research reactor or where a research reactor is planned are listed by region
in Table 1.
The status of research reactors in RRDB is shown by region in Figure 2.
Figure 1:- Countries with operational research reactors
The age distribution of operational research reactors in the RRDB is shown
in Figure 3. It peaks in the range of 25 to 35 years. In fact, 2.2% of the reactors
are in the age range 40-45 years, 51.5% in the range 30 to 39 years, 23.9% in
the range 20 to 29 years and 13.6% in the range 10 to 19 years.
As shown in Figure 4, a large fraction of operational research reactors are
low power with 46.8% or 139 reactors with a thermal power of 100 kW or less.
Finally, as shown in Figure 5, while the number of research reactors in industrialised countries peaked in 1970, the number in developing countries appears to be still gradually rising. Although the RRDB has a section on fuel, it dose not address the details of spent fuel storage and management. For this reason, a questionnaire on spent fuel management and storage was designed and circulated to research reactor operators for the first time in February 1993. Responses to this first questionnaire and subsequent revisions sent to selected research reactors revealed a number of deficiencies in the design of the questionnaire, which have been rectified in the current version (Appendix 1). This latest version will be circulated to research reactor operators world-wide in 1997. An overview of the responses received to date, compiled in the RRSFDB, is presented in the next section.
Figure 2:- Research reactor status.
Figure 3:- Number of reactors versus years in operation
Figure 4:- Power distribution of operational research reactors.
Figure 5:- Reactors in industrialised and developing countries.
3. Spent Fuel Management and Storage
At present, the RRSFDB contains 177 entries dealing with the fuel from 179
reactors, since in two instances the fuel from two reactors is stored at the
same location. Of these research reactors, 23 are permanently shut down, 5 are
temporarily shut down for refurbishment and the remaining 149 are operational.
Spent fuel is usually an ongoing liability after a reactor is shut down and
the IAEA would like to include details of spent fuel from all of the known 272
shut-down reactors reported in RRDB. In addition, there is a large discrepancy
between the 296 operational reactors in RRDB and the 179 reactors that have
so far responded to the questionnaires for RRSFDB. Clearly, some research reactor
operators have lost interest in filling-in questionnaires, especially if they
cannot see the usefulness of the end result. Nevertheless, it is essential for
the IAEA to get a clear and accurate picture of the problems faced by research
reactor operators and their concerns about management, storage and ultimate
disposal of spent fuel, in order to be able to address them and to exert pressure
internationally for the implementation of spent fuel take-back programmes by
supplier countries and to begin a dialogue about possible regional repositories
as an ultimate solution for countries with no nuclear power programme.
The remainder of this section is divided into two parts. The first deals with
numbers of fuel assemblies, their types, enrichment, origin of enrichment and
geological distribution among the industrialised and developed countries of
the world. The second is devoted to fuel management practices in wet and dry
storage facilities and the concerns of reactor operators about long-term storage
of their spent fuel.
3.1. Accumulated Spent Fuel
Figure 6 shows cross-sections of the main Western research reactor fuel assembly
geometries , while the cross-sections of the main Russian types are shown
in Figures 1 to 4 of the paper by N. V. Arkhangelsky . The assembly types
shown in Figure 6 are MTR box-types containing 10-24 fuel plates per assembly,
involute core assemblies containing 280 plates (High Flux Reactor, Grenoble
France), tubular fuel assemblies with 4-6 fuelled tubes per assembly (BR-2,
Belgium and Dido, UK), Triga fuel rod clusters with 1-25 rods per cluster (Triga,
Republic of Korea - single rods, Triga, Romania - 25 rods per cluster), and
pin assemblies with 1-12 pins per assembly (Slowpoke, Canada - single pins,
NRU, Canada - 12 pins). All of these assemblies are about 60-90 cm long, except
for NRU (275 cm) and Slowpoke fuel pins (30 cm). In Russian designed research
reactors, a large variety of fuel assembly geometries have been used. Four of
the more important types are shown in Figures 1 to 4 of reference  and can
be divided into two groups; multi-tube assemblies (IRT-3M and WWR-M) and multi-rod
assemblies (CM-2 and RG-1M). The active parts of these assemblies vary in length
from 35-200 cm.
Most research reactor fuels are shipped in assembly form. For this reason,
in RRSFDB spent fuel numbers are recorded in assemblies, where a fuel assembly
is defined as "the smallest fuel unit that can be moved during normal reactor
operation or storage". Even so, questions regarding numbers of fuel assemblies
obviously caused confusion to respondents to the questionnaires. Consequently,
the data received has been reviewed and corrected by a panel of experts who
know the details of the various fuel assembly designs. At any particular facility,
several different spent fuel types or spent fuels of different enrichments are
usually stored. For example, the store may contain one or more types of HEU
from prior to core conversion and one or more types of LEU following conversion.
Figure 6:- Selected Western fuel geometries.
Very few facilities report more than three types of spent fuel and for this
reason the records in RRSFDB store up to three fuel types per facility. Strictly
speaking, fuels enriched to 20% 235U are classified as HEU. Since many facilities
with LEU cite a nominal enrichment of 20%, we have modified the definition of
LEU to be 20% 235U for the purposes of RRSFDB.
The distribution of fuel types among the reactors in the RRSFDB is shown in
Figure 7. Although the majority are of MTR or Triga types, a significant percentage
(25%) are classified as other types which underlines the fact that many experimental
and exotic fuels exist at research reactors around the world, posing problems
for their continued storage, transportation and ultimate disposal.
The regional distribution of spent fuel, with a distinction made between developing
and industrialised countries, is shown in Figure 8. As might be expected, the
majority of spent fuel assemblies are stored in the industrialised countries.
The origins of the enrichments of the RRSFDB spent fuel inventory is broken
down into fuel of US, Russian, Chinese or other origin in Figure 9. In this
case, others include France, UK, South Africa, natural uranium fuels and those
cases where the origin of enrichment was not known or simply left blank on the
questionnaire. As expected, the US supplied all of the enriched fuel in North
America and most of that in the Industrialised Pacific, while Russia (or the
former Soviet Union) supplied most of the enriched fuel in Eastern Europe. Somewhat
surprisingly, the US was not the major supplier of enrichment in Western Europe.
The breakdown between HEU and LEU is shown in Figure 10. Of interest in this
Figure is the fact that HEU outweighs LEU in North America, whereas the reverse
is true in Western Europe. To some extent this is because more research reactors
in Western Europe have undergone core conversion than is the case in North America.
HEU also outweighs LEU in Africa and the Middle East, Eastern Europe and the
Industrialised Pacific. It is worth noting that a significant fraction of Russian-origin
HEU was originally enriched to only 36%, while most US-origin HEU was originally
enriched to 90%.
Figure 7:- Distribution of fuel types.
Figure 8:- Geographical distribution of spent fuel assemblies.
Figure 9:-Geographical distribution of spent fuel by supplier country.
Figure 10:- Geographical distribution of spent fuel by enrichment.
The breakdown of US-origin fuel, classified as HEU or LEU, is shown in Figure 11. This involves totals of 6,861 HEU and 4,321 LEU assemblies. A similar chart of Russian-origin fuel is shown in Figure 12 and involves totals of 9,683 HEU and 2,877 LEU assemblies. The numbers of US-origin and Russian-origin HEU and LEU spent fuel assemblies at foreign research reactors which might be involved in take-back programmes are compared in Figure 13.
Figure 11:- Geographical distribution of US-origin fuel.
Overall, there are 32,421 spent fuel assemblies stored in the facilities that have responded to the RRSFDB questionnaires to date and another 9,950 assemblies in the standard cores. Of these 32,421, 23,576 are in industrialised countries and 8,842 are in developing countries, while 18,080 are HEU and 14,341 are LEU. At present 7,560 spent fuel assemblies of US-origin are located at foreign research reactors, while the equivalent number of Russian-origin is 8898. As mentioned above, RRSFDB involves only a limited number of the known research reactors in the world, nevertheless these data give an idea of the scope of the problem represented by research reactor fuels. On the basis of these data and a rough knowledge of the numbers of assemblies used each year, it would be possible to make projections for the numbers of spent fuel assemblies that will be accumulated in the future. However, this task is deferred until RRSFDB is more complete, so that any projections eventually made will be more meaningful.
Figure 12:- Geographical distribution of Russian-origin fuel.
Figure 13:- Spent fuel at foreign research reactors.
3.2. Wet and Dry Storage
As shown in Figure 14, by far the most commonly used form of spent fuel storage is the at-reactor pool, pond or basin. Since the average age of these facilities in the RRSFDB is 23 years, the success of wet storage where the water chemistry has been well controlled is remarkable. In fact, many aluminium clad MTR fuels and aluminium pool liners show few, if any, signs of either pitting corrosion or general corrosion after more than 30 years of exposure to research reactor water. As shown in Figure 15, many facilities also have an auxiliary away-from-reactor pool or dry well. At away-from-reactor facilities, the trend is to transition fuel from wet storage to dry storage, which avoids some of the expense of water treatment facilities and their maintenance.
Figure 14:- At-reactor spent fuel storage facilities.
Figure 15:- Away-from-reactor spent fuel storage facilities.
The parameters typically monitored at wet storage facilities are shown in Table
2. Details of the frequency of monitoring and/or control of these parameters
are contained in RRSFDB. They show a remarkable variation from continuous monitoring
to "routine" or "occasional". Because of some inconsistencies
in this data and some obvious confusion over the questions asked in the original
questionnaire, further analysis of the data must await the responses to the
next round of questionnaires.
Similar results for dry storage are shown in Table 3. Clearly, dry storage
requires less monitoring and maintenance than wet storage and at most dry storage
facilities the operators are content to monitor the activity continuously. Again,
more detailed analysis of the dry storage data should await the responses to
the next round of questionnaires.
The concerns expressed by reactor operators about their spent fuel are listed
in Table 4. Not surprisingly, the majority are concerned about the final disposal
of their fuel. This is followed by concerns about limited storage capacity,
finances, cask availability, interim storage diminishing self-protection of
the spent fuel as it ages and the age of facilities and equipment with the consequent
degradation of materials. Some expressed only a single concern but many expressed
Plans for increasing either the number of spent fuel racks, facility size or
both are charted in Figure 16. These numbers reflect the concerns about storage
capacity, interim storage and emergency core unload listed in Table 4. Crane
capacity is another area of concern, especially for some facilities who hope
to ship fuel back to its country of origin in the near future, as is the availability
of suitable transport casks.
Finally, the availability of an internal transfer flask at the facilities in RRSFDB is charted in Figure 17. Surprisingly, 27% of the facilities have no internal transfer flask.
Figure 16:- Planned expansion at spent fuel facilities.
Figure 17:- Internal transfer flask availability.
4. IAEA Activities on Research Reactor Spent Fuels
Besides compiling and maintaining the RRSFDB, and supporting RERTR, the Agency
has been involved as an observer in almost all of the meetings of the "ad
hoc" group of research reactor operators, known as the Edlow/Egan Group.
Over the period from January 1992 until the publication of the Record of Decision
last May this Group kept up unrelenting pressure on DOE to accept US-origin
spent fuel from foreign research reactors and is largely responsible for the
fact the desired programme is now being implemented. Towards this same end,
the Director General of the IAEA, Dr. Hans Blix, has written letters to Secretary
O'Leary of the US DOE (1 July 1993) and Mr. Victor Michailov, Minister of Atomic
Energy of the Russian Federation, (2 February 1995) suggesting that these major
partners in RERTR could facilitate the non-proliferation goal of RERTR by taking
back foreign research reactor fuel.
In response to request from the US Government, the Agency plans activities
to help Member States to prepare their spent fuel for shipment back to its country
of origin.. A major activity in this area is this training course held at Argonne
National Laboratory, USA 13-24 January 1997.
The preparation of a Safety Guide on Design, Operation and Safety Analysis
Report for Spent Fuel Storage Facilities at Research Reactors is well underway.
During 1996 the IAEA convened a Technical Committee Meeting/Workshop in Budapest,
Hungary, to collect and evaluate information on procedures and techniques for
the management of failed fuels from research reactors. Also, the Agency offers
advice through IFMAP, the Irradiated Fuel Management Advisory Programme, to
operators of spent fuel storage facilities and more tangible assistance to developing
Member States through the IAEA's Technical Assistance and Co-operation programmes.
Recognising that the degradation of materials, equipment and facilities through
ageing is becoming of more concern to many operators, the Agency organises several
activities in the materials' science field. Prominent among these is the preparation
of a document on the durability of nuclear fuels and components in wet storage
which is nearing completion. This draft document contains information on aluminium
clad fuels used in research reactors compiled by the participants in a Co-ordinated
Research Programme (CRP) on Irradiation Enhanced Degradation of Materials in
Spent Fuel Storage Facilities. Another CRP is devoted specifically to research
reactor fuel cladding (aluminium alloys) and focuses on the monitoring and control
of corrosion in wet storage. These programmes are supplemented by a series of
Regional Workshops organised by the IAEA to deal with all aspects of spent fuel
handling, management, storage and preparation for shipment.
In recent years the problems of spent fuel from research reactors have received
increasing attention as concerns about ageing fuel storage facilities, their
life extension and the ultimate disposal of spent fuel loom larger. The overall
scope of these problems can be gauged by examination of the databases compiled
and maintained by the IAEA. It is clear that more exposure of the problems and
concerns and more international co-operation will be necessary to resolve the
outstanding issues. It is also clear that take-back programmes of foreign research
reactor fuel will not continue indefinitely. At some stage in the not too distant
future (10 years in the case of the US take-back programme), research reactor
operators will be faced with the permanent disposal of their spent fuel. For
countries with no nuclear power programme, the construction of geological repositories
for the relatively small amounts of spent fuel from one or two research reactors
does not seem practicable. For such countries, access to a regional repository
for research reactor fuel would be an ideal solution. The time is ripe for serious
discussion of regional repositories and to begin planning for the day when neither
take-back programmes nor the reprocessing option might be available.
 Directory of Nuclear Research Reactors, IAEA, Vienna 1989.
 Nuclear Research Reactors in the World, IAEA Reference Data Series No. 3, December 1995 Edition.
 J. E. Matos, Foreign Research Reactor Spent Nuclear Fuel Inventories Containing HEU and LEU of US-origin, Proceedings of RERTR 1994, Williamsburg, USA.
 N. V. Arkhangelsky, The Problems of Treatment of Irradiated Fuel at Russian Research Reactors, IAEA-TECDOC 900, August 1996.