This presentation summarizes the history and status of the main European
research programs (cordis.europa.eu) with Th use. These programs concerned
HTRs, LWRs, and MSRs. Emphasis is given here on the latest two developments.
18.2 Thorium European Research Programme History
During the early years of nuclear energy R&D in Europe, between 1960 and 1980,
the main experimental projects involving Th fuels were related to the HTRs
(DRAGON OECD international project in the UK, ATR and THTR reactors in
Germany) and also to an irradiation of Th-MOX fuel in the Lingen BWR in
Germany. These projects can be seen as scientific successes, but they were not
pursued on a commercial basis because of the priority given in Europe to the
development of LWRs (except in the UK, where low-temperature gas-cooled
reactors were developed), with UO 2 as reference fuel, and, for countries having
selected the reprocessing cycle strategy, the recycling of the recovered Pu as
MOX fuel.
Afterward, several studies were undertaken to examine worldwide interest in
Th. In 1997, M. Lung wrote a report entitled “A present review of the thorium fuel
cycle” [1] at the request of the European Commission. Then, in the 4th EURATOM
Framework Programme, a review of the benefits of the Th cycle as a waste
management option was carried out [2].
As a result of these studies, it was recognized that this option presented major
advantages in term of actinides management through the “burning” of excess Pu in
a non-U matrix (Th oxide), at least for those countries in Europe that considered Pu
as a waste and not a source of energy for future utilization in fast reactors. These
assessments opened the door to several European irradiation experiments during the
5th EURATOM Framework Programme using Th-MOX, namely in the KWO PWR
in Obrigheim (Germany), in the HFR MTR in the Netherland (operated by NRG),
and in the BR2 MTR in Mol (SCK•CEN) (“THORIUM CYCLE [3]” and “OMICO
[4]” projects). These efforts were pursued and completed within the 6th
EURATOM Framework Programme, with the demonstration at laboratory scale
that this fuel would behave in a comparable way as current MOX fuel (see
Sect. 18.3). In the 6th EURATOM Framework Programme, the fuels irradiated in
the programs THORIUM CYCLE and OMICO were further investigated
(postirradiation examination, radiochemical analysis, and leaching tests) in the
“LWR-DEPUTY” project [5] and a strategy study on the “Impact of Partitioning,
Transmutation and Waste Reduction Technologies on the Final Nuclear Waste
Disposal” (“RED-IMPACT”) was performed [6].
In parallel, efforts at the European level started in early 2000 and are still under
way concerning the development of the MSR, using a Th233 U cycle in liquid Th
fluoride fuel. Between the 5th and the 7th EURATOM Framework Programmes,
several projects (MOST, ALISIA, EVOL) were funded (see Sect. 18.4).
18 Overview of European Experience with Thorium Fuels
199
research programs (cordis.europa.eu) with Th use. These programs concerned
HTRs, LWRs, and MSRs. Emphasis is given here on the latest two developments.
18.2 Thorium European Research Programme History
During the early years of nuclear energy R&D in Europe, between 1960 and 1980,
the main experimental projects involving Th fuels were related to the HTRs
(DRAGON OECD international project in the UK, ATR and THTR reactors in
Germany) and also to an irradiation of Th-MOX fuel in the Lingen BWR in
Germany. These projects can be seen as scientific successes, but they were not
pursued on a commercial basis because of the priority given in Europe to the
development of LWRs (except in the UK, where low-temperature gas-cooled
reactors were developed), with UO 2 as reference fuel, and, for countries having
selected the reprocessing cycle strategy, the recycling of the recovered Pu as
MOX fuel.
Afterward, several studies were undertaken to examine worldwide interest in
Th. In 1997, M. Lung wrote a report entitled “A present review of the thorium fuel
cycle” [1] at the request of the European Commission. Then, in the 4th EURATOM
Framework Programme, a review of the benefits of the Th cycle as a waste
management option was carried out [2].
As a result of these studies, it was recognized that this option presented major
advantages in term of actinides management through the “burning” of excess Pu in
a non-U matrix (Th oxide), at least for those countries in Europe that considered Pu
as a waste and not a source of energy for future utilization in fast reactors. These
assessments opened the door to several European irradiation experiments during the
5th EURATOM Framework Programme using Th-MOX, namely in the KWO PWR
in Obrigheim (Germany), in the HFR MTR in the Netherland (operated by NRG),
and in the BR2 MTR in Mol (SCK•CEN) (“THORIUM CYCLE [3]” and “OMICO
[4]” projects). These efforts were pursued and completed within the 6th
EURATOM Framework Programme, with the demonstration at laboratory scale
that this fuel would behave in a comparable way as current MOX fuel (see
Sect. 18.3). In the 6th EURATOM Framework Programme, the fuels irradiated in
the programs THORIUM CYCLE and OMICO were further investigated
(postirradiation examination, radiochemical analysis, and leaching tests) in the
“LWR-DEPUTY” project [5] and a strategy study on the “Impact of Partitioning,
Transmutation and Waste Reduction Technologies on the Final Nuclear Waste
Disposal” (“RED-IMPACT”) was performed [6].
In parallel, efforts at the European level started in early 2000 and are still under
way concerning the development of the MSR, using a Th233 U cycle in liquid Th
fluoride fuel. Between the 5th and the 7th EURATOM Framework Programmes,
several projects (MOST, ALISIA, EVOL) were funded (see Sect. 18.4).
18 Overview of European Experience with Thorium Fuels
199