The 12th International Conference on Environmental ... - Events

Abstracts Session 16
2) STRATEGIC PLAN FOR THE MANAGEMENT OF SPENT NUCLEAR PLAN - 16024
Hitesh Nigam, Edgardo (Gary) DeLeon, Department of Energy, Washington, DC,United States
<strong>The</strong> Nuclear Waste Policy Act of 1982 established geologic disposal as the United States policy for disposal of spent nuclear
fuel (SNF) and high-level radioactive waste (HLW). <strong>The</strong> Department of Energy (DOE) has established programs and plans to disposition
its SNF and HLW at the geologic repository in accordance with this Act. <strong>The</strong> DOE Office of Civilian Radioactive Waste
Management is responsible for the disposition of all DOE managed SNF, commercial SNF, and HLW. Yucca Mountain in Nevada
has been selected as the geologic repository site and is planned to commence operation in 2020. <strong>The</strong> DOE Office of Environmental
Management (EM) is responsible for safe, secure, and cost-effective storage of its SNF and HLW, preparing its SNF and HLW
for shipment, and meeting the acceptance criteria of the geologic repository. <strong>The</strong> focus of this presentation is to discuss DOE EM
Strategic Plan for the management of approximately 2,400 metric tons SNF.
EM has to work very diligently with its many stakeholders and protect the environment and the health and safety of workers
and the public to manage its inventory of SNF, which is located primarily at 4 sites around the country. However, EM is also responsible
for managing SNF from many research reactors in the U.S. as well as foreign research reactors. Majority of the EMs SNF is
dry stored, the remaining SNF is in wet storage, with plans to dry store in the future.
3) DISPOSAL TECHNOLOGIES FOR SPENT FUEL FROM GERMAN NUCLEAR POWER PLANTS - 16028
Reinhold Graf, GNS mbH, Essen,Germany, Wolfgang Filbert, DBE Technology GmbH, Peine,Germany, Klaus-Jürgen
Brammer, GNS mbH, 45127 Essen,Germany, Wilhelm Bollingerfehr, DBE Technology GmbH, 31224 Peine,Germany
<strong>The</strong> direct disposal of spent fuel as a part of the current German reference concept was developed as an alternative to spent
fuel reprocessing and vitrified HLW disposal. <strong>The</strong> technical facilities necessary for the implementation of this part of the reference
concept the so called POLLUX-concept, e.g. interim storage buildings for casks containing spent fuel, a pilot conditioning facility,
and a special cask POLLUX for final disposal - have been built. With view to a geological salt formation all handling procedures
for the direct disposal of spent fuel for the repository were tested aboveground in a test facility at a 1:1 scale. To optimise the
reference concept all operational steps have been reviewed for possible improvement. <strong>The</strong> two most promising variants resulting
from this optimisation process for direct disposal of SF are the BSK 3 -concept and the DIREGT-concept. <strong>The</strong> latter one is the most
recent developed concept and has been designed for the direct disposal of large multipurpose casks. Both concepts rely on borehole
emplacement technology, vertical boreholes for the BSK3-concept und horizontal boreholes for the DIREGT-concept. <strong>The</strong>
paper describes these two favoured concept variants and their status as of today with focus on the BSK3-concept.
Supported by the EU and the German Federal Ministry of Economics and Technology DBE TECHNOLOGY GmbH built an
aboveground test facility at a 1:1 scale to simulate all relevant handling procedures for the BSK 3-concept and GNS as representative
of the German utilities provided the procurement of the hard-ware components. Up to now about 200 emplacement cycles have
been performed successfully. <strong>The</strong> emplacement system in total comprises the emplacement device, the borehole lock, a transport
cart, a transfer cask, which will shuttle between the aboveground conditioning facility and the underground repository, and the
BSK3-canister itself, designed to contain fuel rods from three PWR-fuel assemblies with a total of about 1.5 t HM. <strong>The</strong> BSK3-concept
simplifies the operation of the repository by using the same handling procedures and techniques that will be developed for the
disposal of reprocessing residues.
4) CHARACTERISTICS OF THE SPENT FUEL GENERATED IN KOREA - 16227
Dong Hak Kook, Korea Atomic Energy Research Institute, Daejeon,Korea (Republic), Jongwon CHOI, Korea Atomic
Energy Research Institute, Daejon,Korea (Republic), Heuijoo Choi, DongKeun Cho, Korea Atomic Energy Research
Institute, Daejeon,Korea (Republic)
Nuclear power has satisfied the national electric power demand for three decades, and there are only two reactor types in Korea.
<strong>The</strong> nuclear fuel species, however, have a large variety of fuel types, dimensions, initial enrichment, and fuel supply vendors. A
spent fuel accumulation problem has arisen like any other country that uses nuclear power. <strong>The</strong> spent fuel wet storage capacity in
the reactor pool is getting close to its limit, and so hence, short & long-term solutions are being actively proposed.
First the general status for the nuclear industries and spent fuels will be introduced, then spent fuel characteristics will follow,
and last the future anticipation of spent fuel management will close this article.
keywords: spent fuel, characteristic, Korea
5) NEW SAFETY CONCEPT FOR GEOLOGICAL DISPOSAL IN JAPAN 9 -16339
Kazumi Kitayama, Nuclear Waste Management Organization of Japan, Tokyo,Japan
This paper describes a new safety concept for the Japanese geological disposal program, which is a development of the conventional
multi-barrier system concept. <strong>The</strong> Japanese government established the Nuclear Waste Management Organization of
Japan (NUMO) as an implementation body in 2000 based on the Final disposal actfollowing the publication of the H-12 Report,
which confirmed the scientific and engineering feasibility of HLW geological disposal in Japan. Since then, NUMO has undertaken
further technical developments aimed at achieving safe and efficient implementation of final disposal. <strong>The</strong> safety concept developed
in the H-12 Reportprovides sufficient safety on the basis of site-generic considerations. However, it is considered to be overconservative
and therefore does not represent the most probable performance of the engineered or natural barriers. Recently, concrete
measures have been proposed requiring the safety case to be presented in terms of a realistic assessment of the most probable
performance. This approach takes into account the safety functions of both engineered and natural barriers as well as the longterm
static geochemical equilibrium. In particular, the evolution of the safety performance of engineered and natural barriers can
be efficiently augmented by the realistic long-term geochemical equilibrium.
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