DWIH Tokyo Conference Proceedings

German Research and Innovation Forum Tokyo | Conference Proceedings

German-Japanese Symposium on
Technological and Educational Resources for theDecommissioning of Nuclear Facilities
21 April 2015 | Osaka, Japan

Table of Contents
02

Greetings

03

Decommissioning and Dismantling of Nuclear Facilities –Future Challenges for Technology and Education
Presentations

11• Keynote Lectures13• Session 1: Strategies of Nuclear Dismantling and Decontamination

16• Session 2: Planning and Safety Technologies

21• Session 3: Dismantling and Decontamination

27• Session 4: Waste Management, Conditioning and Final Disposal

31

List of References

32

Editorial Notes
List of Contributors

GREETINGS

2

The decommissioning of nuclear facilities, primarily nuclear power plants, is one of theurgent challenges of the 21st century. With many old reactors reaching the limit of theiroperational time, nuclear engineers and other experts from politics, administration,science and industry need to find solutions of how to minimise the cost and time fordecommissioning and how to pass on the acquired expertise to the next generation.
On 21 April 2015, the German-Japanese Symposium of the German Research andInnovation Forum Tokyo together with the co-organisers University of Fukui, Technische
Universität Dresden and the Japanese-German Center Berlin provided a platform forJapanese and German experts to meet and exchange views on cutting-edge technology

as well as the current state of education and R&D in the field of nuclear decommissioning
and decontamination.

The Japanese and German experts discussed the role of knowledge management systems
and the use of robots and innovative cutting tools in successful and cost-effective

decommissioning projects. Furthermore, German experts presented their practical experience with large-scale decommissioning projects, while Japanese experts highlighted
the current state of the ongoing decommissioning efforts at the site of the crippled
Fukushima No. 1 nuclear power plant.

We are pleased to present the Symposium’s proceedings to you in the hope that this will
help to make its outcomes known to the wider academic community and the generalpublic.

Marcus Schürmann

German Research and Innovation Forum Tokyo

Chief Executive Officer, German Chamber of Commerce and Industry in Japan
Professor Dr. Antonio Hurtado

Director, Institute of Power Engineering and Full Professor of Hydrogen and
Nuclear Energy, Technische Universität Dresden
Professor Dr. Satoshi Yanagihara

Professor of Nuclear Decommissioning and Radioactive Waste Management,

Graduate School of Engineering and Research Institute of Nuclear Engineering,
University of Fukui

Dr. Wolfgang Brenn

Head of Project Management, Japanese-German Center Berlin

INTRODUCTORY STATEMENT

Decommissioning and Dismantling of Nuclear Facilities –Future Challenge for Technology and Education

Dr. Anton Philipp Anthofer and Prof. Dr. Antonio Hurtado
Nuclear Decommissioning and Dismantling (D&D)

There are three phases involved in the peaceful use of nuclear energy: set up, operationand decommissioning and dismantling (D&D). D&D is relevant to all nuclear facilities
where nuclear fuel has been used at any time. In 2014, 434 reactors were in operation
around the world and 72 new construction projects are planned [1]. Nuclear dismantlingowes its complexity to the radioactive material which has been activated or contaminated during reactor operation. The objective of nuclear dismantling is to minimise
radioactive waste, maximise the amount of recycled material and minimise the personal
exposure. Activation of metal materials by neutron radiation can be minimised by selection of suitable metal. Contamination can be minimised by ensuring that safety barriers
at the nuclear facility are secure. In both cases however, nuclear waste and the necessityof decontamination procedures is unavoidable. Moreover, damage to fuel rods, minor
leaks, nuclear incidents or even accidents increase the complexity of nuclear dismantling.
Figure 1 shows the possible treatment route of residual materials from nuclear dismantling and an example of the generated amounts. A simplified decision-making tree isshown in Figure 1 A. Decontamination or after-treatment of the building structures isnormally necessary before the dismantling work starts. Large components or components that are difficult to reach can be dismantled and disassembled before decontamination. The residual material can be assigned to a particular disposal route based on its
characteristics: unrestricted release of residual materials, disposal as radioactive waste or– depending on the material and radioactivity – landfilling. Contaminated or activatedmaterial can be decontaminated in order to reduce the activity to below permissible
limits. If a single decontamination process is not able to achieve the required dose limit
for an unrestricted release, it is possible to continue the decontamination process if istechnologically, economically and ecologically feasible to do so.

3

INTRODUCTORY STATEMENT

4

Figure 1: Residual material from nuclear D&D and its disposal objectives

A: Decision-making tree for the separation into disposal objectives and treatment ofresidual material [2]B: Example of separation of residual material of a pressurized water reactor (PWR) [3]
According to the data of VGB [3], Figure 1 B shows the compounds of a typical control
area of a pressurized water reactor (PWR) with an overall mass of 156,500 Mg. This total
mass is divided into 143,000 Mg of concrete and 13,500 Mg of metallic plant components. Metallic plant components are split into different disposal routes: 9,800 Mg can bereleased without restriction, 700 Mg are provided for landfilling and 3,000 Mg must be
disposed of as radioactive waste. After the treatment of concrete structures, only 600 Mgof radioactive waste remains. The decontamination and dismantling procedures cause
500 Mg of secondary waste - including tools, personal safety equipment and secondary
material such as abrasive materials [3].
The costs of D&D are covered by the nuclear plant operators. The Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) [2] estimates that the cost of D&D for a PWR is €700 m. The IAEA [4] on the other hand estimates that the cost per nuclear power plantis between € 0.5 and € 1.0 billion. The cost of D&D of research and prototype reactors iscovered by the public administration – in Germany the total costs amount to € 10 to 15
billion [2].
State of the Art and R&D on Dismantling and Decommissioning (D&D)

According to Noyes [5], the total D&D process includes the following five steps:

1) Facility shutdown and strategic planning of D&D.
2) Surveillance and maintenance.
3) Sampling, imaging and characterisation.
4) Decontamination and dismantling.
5) Recycling and disposal.
Strategic planning includes the decision as to whether the plant should be dismantled
directly or if a safe enclosure over 30 years is more advantageous. A decision is takenon the basis of technological, economic and socio-economic criteria. Objectives of
R&D activities are the enhancement of strategic planning of D&D by optimising thesequences of operations and reducing the D&D costs caused by the design phases and theselection of technologies. Furthermore, R&D activities focus on the development of newtechnologies for decontamination and dismantling in order to minimise primary andsecondary radioactive waste. The development of manipulated or automated technologies in particular helps to optimise the D&D activities, as the staff can work remotely.
Possible fields of action are demonstrated here using D&D of the German BWR Nuclear
Power Plant (NPP) in Würgassen as an example. Figure 2 shows the phases of D&D at
the Würgassen NPP [6].
Figure 2: Phases of D&D at the Würgassen NPP [6]5INTRODUCTORY STATEMENT

6

In the case of BWR, space for storage and working can be created by the clearance of theturbine house in Phase I. The PWR presents challenges in relation to creating working
space in the containment. Phase II involves the dismantling of the reactor pressure vessel
and the biological shield around it, which is explained in detail in Figure 3. The main taskof Phase III and IV is the demolition, decontamination and dismantling of components
inside the containment. The complexity of these operations is caused by a high activity
and contamination of material inside the containment.
Owing to this special complexity, the reactor pressure vessel of phase IV must be disassembled due to the activation of the high-alloyed steel and its geometric dimensions.
Figure 3 shows the manipulated dismantling procedure of the reactor pressure vessel andthe biological shield of NPP Würgassen [7], which is dealt with in Phase II.
Figure 3: Dismantling of the reactor pressure vessel of the Würgassen NPP [7]

In this case, water jet cutting with added abrasive is used to cut the high-alloyed steel ofthe pressure vessel. This procedure works well under water. The single segments can betaken and stored in the reactor pool. As shown in Figure 3, the biological shield is cut
using heavy-duty wire and blade saws.

Due to the high amount of dust and secondary waste caused by mechanical cutting, thermal cutting technologies are to be used in future D&D projects for the segmentation of
the reactor pressure vessel. To reduce primary and secondary waste, the decontamination
technologies have been developed further. In particular, a change from chemical-abrasive
and mechanical decontamination technologies to laser-based thermal decontamination
has been made, as is the case with Anthofer [8] and [9].
Situation in Germany and JapanAs a reaction to the accident at the Fukushima Dai-ichi Nuclear Power Plant in March
2011, the governments of Japan and Germany decided to shut down their nuclear plants.
According to media reports from January 2015, five Japanese nuclear power reactors
will remain shut down [10] indefinitely. The extent to which the remaining nuclear
power plants will be used still remains unclear. Figure 4 provides an overview of Japanese nuclear plants, and their links to utility companies and reactor types such as BWR,
advanced BWR (ABWR), PWR and advanced PWR (APWR).
Figure 4: Nuclear Plants in Japan [10]7INTRODUCTORY STATEMENT

8In Germany, the seven oldest nuclear reactors and the nuclear power plant Krümmel
were shut down immediately after the Fukushima accident. Moreover, the German government decided to shut down all German nuclear plants successively until 2022. Table 1
lists the German nuclear power plants, by type, BWR and PWR, electrical power, operator and start of commercial operation. Furthermore, Table 1 shows the scheduled date of
the shut down. The timetable indicates that from 2022 onwards, Germany has to manage
17 dismantling projects.
Table 1: Overview of German nuclear power plants [11]Commercial
Operator
operation

Plant

Type

MWel

Biblis A

PWR

1,167

Feb 75

Neckarwestheim 1

PWR

785

Brunsbüttel

BWR

771

Biblis B

PWR

1,240

Jan 77

Isar 1

BWR

878

Mrz 79Unterweser

PWR

1,345

Sep 79Phillipsburg 1

BWR

890

Mrz 80Krümmel

BWR

1,260

Mrz 84

Vattenfall

Total shut down
(8)

March 2011
Provisionallyscheduled 2010 agreed shutdown
shut-down
2001

shut-down& May 2011
closure plan

RWE

2008

2016

Shut-downDez 76

EnBW

2009

2017

Shut-down

Feb 77

Vattenfall

2009

2018

Shut-down

RWE

2011

2018

Shut-down

E.ON

2011

2019

Shut-down

E.ON

2012

2020

Shut-down

EnBW

2012

2026

Shut-down

2016

2030

Shut-down

8,336

Grafenrheinfeld

PWR

1,275

Jun 82

E.ON

2014

2028

May 2015

Gundremmingen B

BWR

1,284

Apr 84

RWE

2016

2030

end 2017

Gundremmingen C

BWR

1,288

Jan 85

RWE

2016

2030

2021

Grohnde

PWR

1,360

Feb 85

E.ON

2017

2031

2021

Phillipsburg 2

PWR

1,392

Apr 85

EnBW

2018

2032

2019

Brokdorf

PWR

1,370

Dez 86

E.ON

2019

2033

2021

Isar 2PWR

1,400

Apr 88

E.ON

2020

2034

2022

Emsland

PWR

1,329

Jun 88

RWE

2021

2035

2022

Neckarwestheim 2

PWR

1,305

Apr 89

EnBW

2022

2036

2022

Total operating (9)12,003

Total (17)20,339

The plants which were shut down in 2011 are now awaiting the start of the D&D process.
At the moment, D&D projects for small NPPs are scheduled, e. g. Stade, Würgassen or
Gundremmingen. Table 1 shows the planned shutdown and the electric power of the
NPPs. This illustrates that D&D for the big plants with high-capacities will start fromnow on. The number of plants, and the residual masses to be treated, will increase significantly.
Due to several projects running parallel, Germany and Japan must combine their efforts
in an integral project management and exchange their technological developments andresearch results in order to handle the residual materials and to produce a maximum ofrecycled material.
Future Challenge for Technology and Education

There are several ways to optimise the D&D process in order to fulfill the challenges ofwaste reduction, especially in terms of minimising secondary waste. Potential lies mainly
within the economical, ecological and technological fields. Moreover, social challenges
of interim and final storage must also be considered.
German federal research on D&D is financed by the German Federal Ministry of Education and Research. The federal research strategy for development of D&D technologies isadministrated by the Project Management Agency Karlsruhe (PTKA), which is part ofKarlsruhe Institute of Technology.
State of the art D&D technologies are applied at the Stade and Würgassen NPPs, whichwere operated by E.ON [6] and [7]. In addition to the D&D of NPPs, research and pilot
reactors have to be dismantled as well. One example is the Rossendorf Research Reactor.
An examination of the operational D&D projects of research reactors highlights initialaspects of strategic planning, including technology application and development, radiation protection concepts and measurement instrumentation.
Reduction of secondary waste is also possible by an advanced treatment of the suspension
material when using water jet abrasive technology, which is developed by Brandauer [12].
An example of an innovative technology in the field of ablation of heavily-reinforced
concrete structures is made by Hess [13]. Assemblies that are very difficult to access, suchas pipes of steam generators, can be decontaminated by high-pressure water, as demonstrated by Finkenberg of RST GmbH [14].
To reduce the personal exposure of the staff engaged in such decommissioning projects,
further advances in robotic and manipulator systems are required. Scientists at the Karlsruhe Institute of Technology (KIT), Kern [15] and Mende [16], designed a path-optimised
manipulator-system, which can be combined with laser technology. The dismantling of9

INTRODUCTORY STATEMENT

10compounds in high radiation areas is only possible by using manipulator technology. For
operational handling, Wälischmiller develops manipulator-based dismantling solutions,as demonstrated by Metzger [17]. IABG realised a remote-controlled manipulator unit forintervention in nuclear disasters, which is able to work in high-radiation fields [18].
A major focus of D&D is on the conditioning and final storage of radioactive waste. The
Forschungszentrum Jülich is running several research projects concerning the treatmentof radioactive waste and its safe final storage [19], [20].
Several German decommissioning-projects, such as the Stade, Würgassen, and Rossendorf Research Reactor NPPs, are offering initial insights into the area of D&D. The first
iteration of steps to optimise technologies and rationalise operational procedures could
be implemented. A resource-optimised D&D using sophisticated technologies in orderto reduce radioactive waste and increase the recycling rate is a challenge for the international nuclear community. As a consequence, an international exchange of technologicalexperiences, know-how and nuclear education between Germany and Japan is necessary.
The goal of future D&D research and development is to create a coherent and systematic
material cycle taking technological, economic, ecologic and social aspects into account.

Presentations – KEYNOTE LECTURES

Competence and Education in Nuclear Technology in Germany
Professor Dr. Antonio Hurtado and Dr. Anton Anthofer

The accident at the Fukushima Dai-ichi Nuclear Power Plant in March 2011 had worldwide consequences for energy supply strategies, even in Germany. The seven oldest
Nuclear Power Plants (NPPs) as well as the NPP Krümmel as a boiling water reactor
were shut down immediately as a consequence of the events in Japan. As a further consequence, the decision of the German government to gradually phase out operation of
nuclear power plants until 2022 was adopted by the legislature of the country.
Despite the German decision: to secure the safe operation of all German NPPs, to handle
future challenges in the decommissioning of these facilities and to dispose of nuclear
waste, maintaining and advancing nuclear competence is required. In addition, radiation
protection also remains an important issue for medicine and measurement instrumentation. Nuclear strategies of Germany’s neighbouring countries require, among otherthings, a preservation of nuclear competence in order to maintain a level playing field
when discussing and supporting new reactor concepts and performing safety analyses.
Owing to these challenges, German Education and Research came to the conclusion thatin order to make a substantial contribution to nuclear safety it is necessary to adapt tothese boundary conditions which came about quite by chance. The major focus of education will be shifted continuously from GEN II and GEN III reactor safety technologies
to future reactor safety technologies of GEN IV reactors, nuclear dismantling technologies and the field of final disposal. However, to preserve competences in all fields ofnuclear technologies, international cooperation must be intensified in the next few years.

Energy Policy of Japan and the Decommissioning of Fukushima Dai-ichi
Nuclear Power Station

Professor Dr. Hajimu Yamana

Four years have passed since the nuclear accident in 2011. In these four years, the conditions of Fukushima Dai-ichi nuclear power station have been greatly improved.
The emergency situation caused by the accident had settled down by the end of 2011 andthe measures based on the mid-and-long-term roadmap defined by the Japanese government subsequently carried out. Implementing these measures, the removal of spent fuelsfrom Unit 4 has already been completed, most of the rubble accumulated on the operating floor of Unit 3 has been cleaned up, and radiation levels on the site have drastically

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improved. On the other hand, challenging issues, such as the treatment of contaminatedwater, are still being worked on each day, and at the same time the preparation for thedecommissioning work which is due to be carried out in the mid- and long-term future iscurrently underway.
Since last year, an organisational structure was formed to contribute to the decommissioning of Fukushima Dai-ichi by the four parties including the Government, NDF,
International Research Institute for Nuclear Decommissioning (IRID), and TEPCO’s
Decontamination & Decommissioning Engineering Company. NDF developed thedecommissioning technological strategy on the request of the Government, and plays arole in establishing a plan for necessary R&D. Now, “The strategic plan”, the first versionof the decommissioning strategy, is being prepared. The decommissioning strategy isdeveloped from the viewpoint of optimising the risk reduction strategy which focuses on
the retrieval of fuel debris from the reactors and radioactive waste management. Also, it
is essential to develop the various types of technologies required for decommissioning as
in the case of fuel debris retrieval, and this development has been promoted by IRID andis subsidised by the government.
After the nuclear accident, there was confusion surrounding the Japanese energy policy.
At first, there was a large-scale political movement away from nuclear energy because of
the impact of the accident. Owing to the renewal of the Nuclear Safety Regulations, thecritical condition where no nuclear power is generated continued for two years.
Then, driven by the change of administration in Japan, the energy policy started to bedeliberated again and a new basic energy policy was established last April. This new policy focuses on the promotion of renewable energy and maximum reduction of dependency on nuclear power. Also, the purpose of nuclear power generation as an importantbase load power was acknowledged in the policy. The Government is promoting a newenergy mix and cost re-evaluation for each type of power source based on this new energy
plan. The new targets of energy composition and carbon dioxide emission reduction in
Japan, including nuclear power and renewable energy, were established in May 2015.

PresentationS – Session 1

Strategies of Nuclear Dismantling and Decontamination

The Strategies of Research and Education on Decommissioning of Nuclear Facilities in the University of Fukui
Professor Dr. Satoshi Yanagihara

There are 15 nuclear power plants in Fukui prefecture where the University of Fukui islocated. The university has been running a nuclear energy and safety course for 10 years
by taking advantage of its location. The university’s research institute of nuclear engineering located at Tsuruga city has played the role of regional research and education
centre in the wake of the Fukushima accident, focusing on nuclear engineering, nuclear
disaster prevention and risk management and nuclear decommissioning in collaboration
with the private sector and local communities.
The organisation of the special nuclear decommissioning group set up at the university’s
institute is geared towards systemisation of the decommissioning and radioactive waste
management process using the experience and lessons learned at the ongoing Fugen
decommissioning project in order to minimise the environmental burden. The study
includes methodology for optimising the decommissioning and waste treatment process,development of computer systems for decision making, radioactive inventory estimation, computer simulation of decommissioning work activities, knowledge management
on nuclear decommissioning, etc.
In terms of the optimisation study, a decommissioning process is characterised by precise estimation of project parameters such as cost, accumulation of waste and radiation
dosage of workers, for which computer systems have been developed for calculating the
project parameters taking the technology and working conditions to be applied to thedecommissioning project into account. The study also includes research on optimisationof a decommissioning plan and the optimum combination of the technologies deployedusing multi-criteria decision analysis.
The university has also developed an education program on nuclear decommissioning
to cope with expanding demand of the nuclear industry. In addition, the main focus ofdismantling and decontamination activities is on remediation of the Fukushima Daiichi plant. The university is making an effort to measure the remediation throughout thelong project period in cooperation with several universities. Its program includes project
management, characterisation of debris caused by the accident, laser decontamination,etc. as well as education and training in nuclear decommissioning.
While decontamination and decommissioning might be possible using current technology, efficient deployment of current technology is necessary for cost-saving and safety
reasons. In cooperation with local industry and research organisations, the university

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will contribute to improving knowledge management and technology deployment inupcoming decommissioning projects. Education and training on nuclear decommissioning is important for young people studying and developing a career in this area. The goalof the university in this field is to serve as a regional centre for the promotion of safe andefficient nuclear decommissioning.

German Federal Research on Technologies for Decommissioning and Dismantling of Nuclear Facilities
Dr. Michael Weigl

Since 1956, nuclear research and development (R&D) in Germany has been supportedby the Federal Government. The goal was to help German industry to become competitive in all fields of nuclear technology. National research centres were established anddemonstration plants were built. In the meantime, all these facilities were shut down andare currently being decommissioned and dismantled (D&D).
Meanwhile, Germany is one of the leading countries in the world in the field of D&D.
Two big demonstration plants, the Niederaichbach Nuclear Power Plant (KKN), a
heavy-water cooled pressure tube reactor with carbon-dioxide cooling and the KarlsteinSuperheated Steam Reactor (HDR), a boiling light water reactor with a thermal powerof 100 MW, have been totally dismantled and a “green field” status reached. Another big
project was finished in 2008. The Forschungs-Reaktor Jülich 1 (FRJ1), a research reactor
with a thermal power of 10 MW was completely dismantled and in September 2008 an
oak tree was planted on a green field at the site where the FRJ1 previously stood. This is
another example for German success in the field of D&D.
Within these projects, many new solutions and innovative techniques were tested. These
were developed at German universities and small and medium-sized companies mostly
funded by the Federal Ministry of Education and Research (BMBF). Some examples areunderwater-cutting technologies like plasma arc cutting and contact arc metal cutting.
This clearly shows that research on the field of D&D is important for the future. Moreover, these research activities are important for preserving nuclear engineering know-how
in Germany and will enable enterprises to compete in the expanding market of D&D
services.

Challenges in Nuclear Decommissioning for E.ON –Focus on Decontamination Technologies
Dr. Steffen Pankow

Decontamination technologies – with a focus on decommissioning and dismantling(D&D) of nuclear power plants (NPP) in particular – were the subject of extensive
research and development activities over the last decade and mostly driven by practicalactivities on D&D sites.
The main aspect from E.ON’s point of view is the selection and planning of the best
decontamination strategy in respect to radiation protection and cost optimisation many
years in advance of practical on-site implementation.
Three aspects have to be considered in particular:• Decontamination for radiation protection reasons (ALARA)• Decontamination for the reduction of nuclear waste• Decontamination of equipment for reuse
The presentation provided a short overview on E.ON’s experiences in determination andrealisation of decontamination strategies – i.e. the lessons learned from previous D&D
projects (NPP Würgassen and NPP Stade) as well as the transfer of knowledge to sites
where the D&D process is due to start shortly.
Although E.ON has gained a wealth of experience from decommissioning projects in thelast decade, ultimately the decision-making matrix must still be developed and evaluatedfor each plant individually. Therefore the spotlight of the presentation was directed on
typical questions and possible answers in such a decision-making process.

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PresentationS – Session 2

Planning and Safety Technologies

16

Radiation Protection during Decommissioning of theRossendorf Research Reactor
Professor Dr. Peter Sahre

After obtaining the first licence for decommissioning of the Rossendorf Research Reactor in 1998, the spent fuel of the reactor was removed from the reactor building in 1998.
In 2001 the dismantling of the reactor was started and we anticipate the decommissioning work will be finished in 2018.
The first step was the analysis of the radiological situation. For this we developed together
with a company a system which is able to scan a room or a hot cell automatically by measuring the dose rate and Gamma ray spectrum of each point. Furthermore, in situ Gamma
ray spectrometry and sample analysis measurements have been used to explore the radiological situation. The same methods have been used for clearance measurements. A crossgamma chamber was only used for clearance measurements. The clearance procedurecomprises unrestricted clearance, restricted clearance for demolition of buildings andmaterial for deposit.
The exhausted air of the reactor building was also measured. The resulting effective committed dose for individual members of the general public was lower than 0.1 µSy in eachyear.
In relation to occupational exposure, the collective dose of the staff during the wholedecommissioning time was less than 20 mmanSv and was primarily made up of the internal dose. In order to reduce the internal dose when destroying the shield of the reactor, astable tent including exhaust air was erected.
The decommissioning further included the dismantling of the cask for reactor water
storage, remote-controlled recovery of solid waste and the management of radioactive
waste.

Planning of Knowledge Management System for
Decommissioning of Nuclear Facilities
Dr. Yukihiro Iguchi

The decommissioning of a nuclear facility is a long term project, and involves the handling of information, starting with the design of the project, followed by its execution
and the deconstruction of the facility. Moreover, the decommissioning project is likely tobe prolonged because of the lack of a waste disposal site.

In Japan, the decommissioning projects of the power plants Tokai, Fugen and Hamaoka
1&2 are currently in progress based on past experience with the Power Demonstration
Reactor of the Japan Atomic Energy Agency (JPDR). Moreover, 6 units of Fukushima
Dai-ichi Nuclear Power Plant and 5 normal LWRs will be decommissioned after theaccident caused by the Great East Japan Earthquake.
Because of the social and political circumstances after the accident, the outcome of thedecommissioning is unforeseeable, i.e. the location of the destination of spent fuel andradioactive waste has not been decided. This makes the projects longer and also moredifficult, since the employees with enough experience and knowledge are about to retire.
This situation forces us to seriously consider “Knowledge Management”, such as knowledge preservation, knowledge transfer and education.
IAEA recommended the importance of the “Nuclear Knowledge Management (NKM)”
and has organised international meetings and prepared documents related to knowledge
management (KM) since 2002. They are mainly for the commissioning and operation of
nuclear facilities. Studying KM for decommissioning is recommended.
Because the transfer of knowledge to and education of the next generation is a crucial
issue, integration and implementation of a system for knowledge management is necessary.
On the other hand, the knowledge required for decommissioning is different from theknowledge required for construction or operation. Knowledge of the design of the plantis undoubtedly necessary, but not of the entire plant.
Moreover, because the decommissioning is a long term project; the project lasts several
decades from the start of the deconstruction phase. Consequently, knowledge transferfrom one generation to the next generation is necessary.
We have to arrange, organise and systematise the data and information of the plantdesign, maintenance history, trouble events, waste management records, etc. The collected data, information and records should be organised by a computer support system,e.g. database system, which becomes a base of explicit knowledge.
Moreover, measures for acquiring tacit knowledge from retiring employees are necessary.
The experience of the retirees should be documented as much as possible through aneffective questionnaire or interview process.
The integrated knowledge mentioned above should be used for the planning and implementation of dismantling or education of the future generation.
In conclusion, a comprehensive knowledge management system (KMS) should be wellplanned in advance for a decommissioning project.

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Remote Control Manipulator Systems for Nuclear Intervention andDecommissioning

Dr. Ahmed Abou-El-Ela and Dr. Guido Kremer

In the event of a nuclear accident or during the dismantling of nuclear installations, mostoperations generally have to be controlled remotely. Highly-specialised equipment technology is required for this. The technical demands are as multifaceted as the intended
spectrum of use and also the work to be carried out – for example, easy to handle sampling systems are just as necessary as heavy demolition machines, or even double-arm
force-feedback manipulators for precision work.
The requirements regarding radiation resistance, intervention capabilities, decontaminability, etc. are very heterogeneous for each case. In the past, a wide variety of systems
were designed that were adapted specifically to the respective task at hand, particularly
the task of dismantling nuclear installations. Usually, these were prototypes as they wereused only for one singular mission. The development expenditure was generally high, andtime-consuming and costly tests had to be carried out to ensure sufficient reliability withthese prototypes.
However, tools and systems are readily available on the market for nearly all tasks related
to nuclear accidents or nuclear decommissioning, but these were originally designed for
operation in a conventional working environment. To control these systems remotely
in contaminated surroundings, they must be converted accordingly – for example,
replacement of functions that are normally operated manually with remotely-controlled
functions, and/or hardening of the electronics against ionising radiation. The necessary
concepts and components of this conversion are largely independent of the type of therespective device or tool itself, and are listed below:• Measurement and control technology• Remote control systems• Video techniques• Data transmission• Visualisation• Control room technology• Enclosures (radiation protection)• etc.

Based on more than 20 years of experience in the conception, specification and testingof remotely-controlled systems acquired in various client projects in the field of nuclear
decommissioning, we have developed a modular concept for converting specialised
vehicles for remotely-controlled operation in contaminated environments. Based on thisconcept, it is possible to retrofit virtually any industrially proven vehicle and therefore
adapt it to the specific requirements in the nuclear field.
With this, development duration and costs can be significantly reduced, while at thesame time improving reliability and availability. The example of the 2014 project “Development of a highly flexible manipulator system (HMS)” demonstrates the conceptual
approach, practical implementation and the achievable performance.

Remote Controlled Manipulator Systems for Decommissioning Process
Jan Hedtstück

Decommissioning of nuclear power plants (NPP) is a complex and long-lasting taskwith high requirements in terms of personnel safety and precise execution of any given
work step. In order to minimise exposure of workers to unsafe and/or radioactive areas,
remote-controlled manipulator systems that are able to perform a variety of tasks insteadof human workers are needed. These tasks include but are not limited to handling ofheavy loads, packing of active waste, handling of tools for cutting, welding etc., or carrying out maintenance on other vital equipment.
For these applications, Wälischmiller Engineering GmbH (HWM) from Markdorf,
Germany is offering a variety of different radiation-resistant master-slave and power
manipulators that are customised for each individual usage site.
The heavy duty A1000 power manipulator, of which almost 100 units have been delivered worldwide since 1979, is suited best for manipulating heavy loads up to 500kg in thegripper and lifting even heavier loads of up to 4t with its load hook.
The robotic power manipulator Telbot offers superior precision and robotic functionality like moving in a Cartesian coordinate frame and the ability to repeat pre-programmed moving patterns while still being strong enough to manipulate objects of up
to 120kg with its gripper. An equally high radiation resistance of 1MGy can be achieved
and all electrical parts like motors and sensors are located in a gearbox outside of themanipulator arm, whereas the arm itself consists only of mechanical parts like torquetubes, links and joints.

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With dozens of NPPs due to reach the end of their service life in the next decade, thepolitical decision in Germany to phase out nuclear energy and the triple disaster in Japanon 3/11, the need for viable decommissioning solutions, field experience of personnel anddecommissioning equipment has increased.
After being used in the successful decommissioning work under the supervision of Energiewerke Nord GmbH (EWN) at Greifswald NPP and Rheinsberg NPP, a manipulator
system consisting of one A1000 packing manipulator and one Telbot tool-handlingmanipulator was moved to its next usage site at Obrigheim NPP.
At Obrigheim, both manipulators were given the task to first cut and then pack the uppercore structure of the PWR reactor in the wet cutting area. By using different cutting
tools, both manipulators successfully cut the complete upper core structure and safely
packed the pieces into Konrad containers for storage while also gathering samples during
this process to determine radioactivity.

PresentationS – Session 3

Dismantling and Decontamination

Robot Technology for Nuclear Decommissioning of Fukushima Dai-ichi NPS
Kiyoshi Oikawa

The International Research Institute for Nuclear Decommissioning (IRID) is a technology research association consisting of 18 member corporations that focus on R&D
required for the decommissioning of the Fukushima Dai-ichi Nuclear Power Station(NPS). We have teamed up with TEPCO’s Fukushima Dai-ichi Decontamination andDecommissioning (D&D) Engineering Company to identify the needs of the Fukushima Dai-ichi NPS site and are engaged in the development of various decommissioning
technologies within an integrated management process. The integrated managementof R&D being carried out by IRID follows the Mid-and-Long-Term Roadmap for theDecommissioning of TEPCO’s Fukushima Dai-ichi NPS Units 1-4 (Mid-and-LongTerm Roadmap).
Total loss of all power sources at Units 1-3 of the Fukushima Dai-ichi NPS disabled thecirculation pumps, thus preventing the flow of water into the Reactor Pressure Vessels(RPVs). Without the necessary water to cool them down, the inside of the RPVs overheated, leading to the melting of the fuel along with control rods and other structuralcomponents. It is assumed that the melted material solidified again after reaching thebottom of the RPVs, and partially at the bottom of the Primary Containment Vessels(PCVs). This solidified material is called “fuel debris.”
The fuel debris retrieval project plans to use the “submersion method”, an approach
whereby fuel debris is fully covered with water. The submersion method helps reduce
unnecessary exposure of workers since water is effective in blocking radiation and preventing dust dispersion during the machining of the debris for its collection. For implementation of the submersion method, water leakage from the PCV walls needs to be
stopped. To do so, the work areas and access routes need to be decontaminated to allow
access by workers, and leakage points must be detected.
Tremendously high radiation levels in and around the PCVs are preventing access byworkers and require the use of remotely-controlled robots. Up until now, IRID has
developed various remotely-controlled robots for decontamination and water leakage
investigation and has conducted tests at the Fukushima Dai-ichi NPS site. In order toassess the damage situation inside the PCVs, and the location and condition of the fueldebris, IRID currently plans to develop remotely-controlled shape-deformation typerobots that can enter the PCVs via a narrow access port. First testing was conducted at
the Fukushima Dai-ichi NPS site in April 2015.

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For the submersion method, IRID will develop technology for cutting and collectingof the fuel debris using the tools on the tip of a retractable manipulator which descends
from the operation floor into the RPV/PCV. Remotely-controlled robot technology isalso required in this case. Meanwhile, considering that fuel debris retrieval may not proceed smoothly by using the submersion method alone, IRID plans to study alternative
methods including in-air work alongside the submersion method.
In order to progress the decommissioning of the Fukushima Dai-ichi NPS, remotely-controlled robots capable of conducting various operations for the workers must be
built and technological innovations developed on the basis of knowledge from aroundthe world.

Innovative Technologies for the Decommissioning of Nuclear Facilities
Martin Brandauer

As part of the German energy transition program, the decision to completely phase-out
nuclear power generation was made abruptly in 2011, after the incident in Fukushima.
As a consequence, eight running facilities were immediately shut-down by law. Thesefacilities were undergoing life-extension procedures at that time and at no point had
been considered for decommissioning. This circumstance resulted in a very long transition phase that is still ongoing. The remaining nine facilities still in operation will be shut
down in the coming years, while a complete phase-out and final shutdown of all facilities
is mandatory by the end of 2022. The final phase-out of nuclear power will, however, only
be possible once all the remaining facilities have been decommissioned.
As a result of the current situation and due to the operators’ decision to opt for a direct
decommissioning strategy, many large scale facilities will be decommissioned simultaneously in Germany in the coming decades; which represents a considerable challenge.
The subject of decommissioning is, however, not a new topic in Germany. There are a
substantial number of facilities which are already in an advanced decommissioning state.
To date, three facilities in Germany have also been completely decommissioned andreturned to the so called “green-field” state, i.e. complete demolition of the facility andreforestation of the former site.
For this reason, decommissioning of nuclear facilities has already proven to be feasible.
Nevertheless, many problems have occurred over the past decades and many lessons had
to be learned. Furthermore, some of the applied techniques are still rudimentary andusually taken from other application fields, without adapting them for the new tasks. The

field of research and education for the decommissioning of nuclear facilities establishedin 2008 at Karlsruhe Institute of Technology (KIT) addresses these technical problems
and advances the development of new technologies and contributes to the education of
new professionals for the industry.
One technology currently being developed at KIT is related to the fast and efficientdecontamination of concrete surfaces. This is an important step in guaranteeing theremoval of all possible contamination from a nuclear facility before releasing it from theatomic law for complete dismantling. This technology is being addressed in two parallel
research projects. The first one is a fully remote-controlled and semi-autonomous manipulator for deployment in radioactively contaminated sites. A virtual model of the site is
created using 2D and 3D laser scanners. Specially developed algorithms process this datafor optimised and efficient decontamination [21].
This manipulator assists the operator in fulfilling the intended task and prevents the staff
from working in contaminated areas. Since this is still a prototype, a follow-up research
project has been set up to develop a very fast and highly efficient decontamination unit inclose cooperation with the industry. This unit is also controlled remotely, can be deployed
and moved by a crawling chassis and has a very high mechanical decontamination rate ofabout 10 m²/h [22].
Another technology that is currently being developed deals with the secondary waste
produced during the water abrasive suspension cutting of activated steel components.
This method has already proven to be highly suitable for application with underwater
manipulators, cutting complex geometries like pressure vessel internals. The main drawback, however, is the concurrent generation of large quantities of secondary waste. For
this reason a physical separation process is being developed, reducing the amount ofwaste by 90 % (essentially the comprised activated steel chips) [23].

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The WAK Decommissioning and Dismantling Project
Dr. Marco Klipfel and Christian Held

The Wiederaufarbeitungsanlage Karlsruhe (WAK) was a pilot nuclear reprocessing
plant for subsequent commercial reprocessing. Nuclear fuels from various experimental
and commercial reactors were reprocessed at the plant. Uranium and plutonium werereused in new fuel elements and the High Active Waste Concentrate left in storage buildings on the site. In 1991, the reprocessing operation was terminated, and the decommissioning of the plant started.
As part of the restructuring, the WAK Rückbau- und Entsorgungs-GmbH (WAK
Decommissioning and Waste Management Company) was committed to all activities
related to the decommissioning of experimental and prototype nuclear facilities, including waste management at the Karlsruhe site.
The following facilities are being decommissioned:• Karlsruhe Reprocessing Plant, including the Vitrification Facility• Compact Sodium-cooled Nuclear Reactor• Multi-purpose Research Reactor• Research Reactor 2• Hot Cells (shut-down sections)• Smaller nuclear research facilities of the KIT after shutdown
The presentation provided a summary of current decommissioning activities. It focussed
on the various concepts for techniques in relation to the remote dismantling of highly
radioactive components.

Approach to the Decommissioning of Large Components utilizing

Decontamination and Segmentation Technologies for the Use of Available
Disposal Options
Andreas RothThe approach for decommissioning of large components, e.g. steam generators, reactor
pressure vessel and its internals, etc., is determined based on overall optimisation whichtakes regulatory and licensing, technical and operational, safety and ALARA, economic and scheduling as well as public-acceptance and stakeholder issues into account.

The main pathways for this material are recycling, clearance or disposal. These options
require different levels of effort at the segmentation, decontamination, waste processing and packaging and transportation process steps. This presentation focussed on thesegmentation process step. During an overall assessment of the most relevant management mode for large component decommissioning, the feasibility of segmenting on thedecommissioning site and storage or disposal in standard containers or removal of thecomponent from the site in one piece, followed by processing or storage offsite is also
considered. However, especially at a damaged site like the Fukushima Dai-ichi site, segmentation technologies have to be used on site to dismantle the damaged equipment andoffsite segmentation is not an alternative.
There are various tried-an-tested segmentation technologies on the market that offerdifferent advantages and disadvantages. There is no best technology, but a toolbox to support a segmentation strategy specific to each project. Thermal segmentation methods,
e.g. autogenous cutting, plasma arc cutting etc., offer high cutting rates, but require very
precise guidance, can often not be used for multiple materials and produce difficult secondary waste like aerosols. A range of heavy-duty conventional mechanical segmentationequipment such as wire saws, disc saws, nippers, grinders, etc. is available. Such tools haveto be designed to manage strong forces due to the direct contact with the component andconsequently need strong and heavy supports and guidance systems.
Water Abrasive Suspension (WAS) jet cutting represents an alternative remote-controlled mechanical segmentation technology which can be used in hazardous environments and has a proven track record in nuclear, demilitarisation as well as off-shore
applications. WAS can be operated in water or air. With this technology, a small andflexible cutting lance can be operated up to a distance of 1,000 m from the high pressure
pumping and suspension mixing units. Intelligent use of sensors, hydrophones and cameras allows the cutting results to be efficiently evaluated remotely. These features and therobust cutting process itself make WAS particularly suitable for application at damagedsites, where access is limited due to a hazardous environment and no precise knowledge
on the geometries and positions of components as well as available space for the cutting
operations can be obtained. Disadvantages of WAS are the secondary waste generationfrom the abraded material and a relatively low cutting rate due to the batch operating
mode. Research and development on continuously-operated nozzles as well as various
efficient capturing systems for the abraded material (e.g. cascades, filters etc.) is being
carried out to minimise these disadvantages.

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Decontamination by High Pressure Water Jetting Systems
Matthias Finkenberg

During decommissioning of nuclear power plants (NPP), decontamination of low andmedium radioactive waste reduces costs and exposure of the personnel.
Well known companies that are already involved in the decommissioning of NPPs
generally use four methods of decontamination: electrolytic decontamination, chemical decontamination, dry blasting, and high-pressure water jetting. The general aim of
decontamination is the reduction of measurable radioactivity so that the material is nolonger considered to be radioactive in a legal sense.
High-pressure water treatment has been found to be an ideal method for cleaning or
decoating contaminated parts. The advantage is that, compared to other mechanicalcleaning methods, much less dust is produced and used water, the cleaning medium, canbe circulated and filtered, which means that no new waste is generated.
The decontamination process for low-level waste by high-pressure water jetting caneither be done manually under full protection of the worker or can be remote-controlled.
The cleaning process is done in a special handling cabin with appropriate systems foradmission of contaminated parts and discharge of cleaned parts as well as special ventilation equipment to provide adequate visibility, filtration and dehumidification. The
construction and all surfaces of the system are designed to minimise accumulation of
any particles. The water used for the high-pressure cleaning process is collected andtransported through a water recovery station where radioactive particles are removed by
special filters.
Very recently a test system was delivered for the fully-automatic, remote-controlleddecontamination of steam generator pipes using high-pressure water up to 3,000 bar.
First tests with this system have shown promising results.
Fully-automated cleaning systems are state of the art for industrial applications and areused whenever a large amount of identical parts need to be cleaned in a short period oftime. Most of the parts that need to be decontaminated during decommissioning of
NPPs are unique in shape and structure so that fully-automated industrial solutions
cannot be adopted directly. The focus of current research activities at RST GmbH is toprovide fully-automated decontamination solutions by a robot in case of higher radiation levels, e.g. working with medium-level waste.

PresentationS – Session 4

SESSION 4: Waste Management, Conditioning and Final Disposal

Waste Management of Structures of Buildings and Containment
Professor Dr. Peter Jehle

What was undoubtedly one of the most serious accidents in the history of the civilian use
of nuclear power, the triple accidents at the Fukushima Dai-ichi NPP on 11 March 2011,
led to the decision of the German government to end the use of nuclear energy in a structured manner. In 2012, a total of 16 nuclear power plant units were already shut down
and in the process of decommissioning. Of the remaining 18 power plant units, 9 arestill in operation at 8 locations. All units have to be shut down in the next few years. The
federal government therefore set the dates for the final shutdown of each of these units
and listed these in the Atomic Energy Act. The last facility is scheduled for shutdown in
2022.
This presentation gave an initial overview of post-operation phases, the decommissioning
process and the decommissioning strategies. An interesting fact here is that in Germany,a standardised set of rules for a mandatory procedure in the decommissioning phase does
not exist currently. The legislative framework of national or international laws, especially§7 of the German Atomic Energy Act, is summed up in the form of a manual and determines the steps of safe enclosure or dismantling of the reactor and nuclear facilities. The
differentiation and classification of radioactive waste is an additional point to be considered.
In the past years, a great deal of experience in decommissioning and demolition of nuclear
power plants has been acquired. In future years we can develop and improve the technical capabilities. An important element will be public acceptance of all these activities.

Research for the Safe Management of Nuclear Waste
Professor Dr. Dirk Bosbach

The safe management of radioactive waste arising from electricity generation including
its ultimate disposal in a deep geological disposal facility is one of the great challengesof our times. Roughly 300 nuclear power plants worldwide will reach the end of theirenvisaged lifetime by 2030 and need to be decommissioned. Technologies for the decommissioning of nuclear facilities and for the safe management of the associated waste havebeen developed in recent decades. Current R&D activities are focussing on optimisationof aspects such as exposure of personnel to radiation, economics, and others.

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However, it seems that some special waste streams arising from the decommissioning of
nuclear installations have not been in the focus of R&D activities in the past. This special waste, some of it referred to as ‘problematic radioactive waste’ by the IAEA, containradioactively contaminated toxic metals such as beryllium, cadmium or mercury, spention-exchange resins, radioactively contaminated NAPL and decontamination fluids,
wastes containing asbestos, PCB, and so on, plus mixed waste with elevated concentrations of chemotoxic/hazardous constituents.
Although the volumes of a number of these special waste streams are expected to becomparatively small, there are specific challenges associated with their safe management,
arising from their associated chemotoxicity, the potential release of radionuclides (during temporary storage and/or under disposal conditions), their incompatibility withestablished conventional treatment and conditioning techniques, analytical challenges
regarding the adequate determination of radioactive and chemotoxic inventories, etc.
The presentation provided an overview of current R&D activities at Forschungszentrum
Jülich in relation to the treatment of some types of special waste and its transformation
into new shapes and forms for safer and more compact storage.

R&D on Treatment and Disposal of Radioactive Waste resulting fromAccident at Fukushima Dai-ichi NPS
Yasuaki Miyamoto

The properties of the waste generated by the accident at the Fukushima Dai-ichi Nuclear
Power Station differ from those of the radioactive waste (waste from operation) generated in a conventional Nuclear Power Station in the following respects (but not exclusively): the waste includes radionuclides originating from the core fuel, it may include
a sea water component resulting from the reactor core cooldown immediately after thetsunami and the accidents, and it includes the zeolite and sludge with high radiation
emission rates for which the results of processing and disposal are not evident at present.
Additionally, the generated amount is also large with various levels of contamination.
In order to improve our prospects of being able to safely process and dispose of this radioactive waste, we implement R&D after understanding different points in relation toconventional radioactive waste.
The Nuclear Damage Compensation and Decommissioning Facilitation Corporation(NDF) performs the role of a Centre of Excellence (COE) in the decommissioning of

the Fukushima Dai-ichi Nuclear Power Station and the implementation of measures forthe treatment of contaminated water, by offering strategy planning, R&D planning andprogress management support in relation to important problems.
According to the government and NDF strategy, the purpose of TEPCO’s Fukushima
Dai-ichi Decontamination and Decommissioning (D&D) Engineering Company is
to implement the decommissioning comprising aspects such as safety control, and theInternational Research Institute for Nuclear Decommissioning (IRID) serves as theorganisation responsible for the development of critical decommissioning technologies
on a mid- and long-term basis
An overview of the processing and disposal of the radioactive waste generated at the Fukushima Dai-ichi Nuclear Power Station is shown in the “Mid-and-Long-Term Roadmap
towards the Decommissioning of TEPCO’s Fukushima Dai-ichi Nuclear Power Station
Units 1-4”. It must be demonstrated that the mentioned milestones “Making Basic Policy
for Processing & Disposing of Solid Waste” and “Confirmation of Prospect on Safety for
Processing & Disposing of Solid Waste” can be reached by 2017 and 2021 respectively.
Apart from the waste from the reactor cores, such as fuel debris, the waste generated at
the Fukushima Dai-ichi Nuclear Power Station can be classified roughly into rubble andfallen trees or secondary waste produced from contaminated water treatment.
The rubble and fallen trees stemming from construction-related activities in the wakeof the accident and subsequent decommissioning, etc., are stored in an area preparedwithin the site of the Fukushima Dai-ichi Nuclear Power Station. Heaps with an air
dose of less than 0.1 mSv/h are accumulated outside, whereas heaps with an air dose of
0.1-1 mSv/h are kept under curing sheet and heaps with an air dose of 1-30 mSv/h are
stored in soil-covered interim storage facilities, temporary storage equipment and vessels.
The high-level radioactive waste is stored in solid waste storage facilities. Fallen trees,branches and leaves are chipped and stored in temporary storage tanks as a measure for
reducing radioactivity levels in the air and the risk of fire. Trunks with low doses areaccumulated outside.
The contaminated water generated by the cooling of the reactor cores is purified by contaminated water treatment facilities consisting of a caesium removal system, a desalination system and the Advanced Liquid Processing System.
The caesium removal system essentially consists of a caesium adsorption device and asecondary caesium absorption vessel, with zeolite, the adsorption material, generated aswaste.

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Although the decontamination device, which is another caesium removal system inwhich the caesium flocculates and settles using nickel ferrocyanide, is no longer in operation, 597 cubic metres of sludge, which would be waste, have been stored. This will notincrease in future.
Radionuclides other than caesium, such as strontium, are removed in the Advanced
Liquid Processing System. At the moment, several Advanced Liquid Processing Systems
are working and an increasing amount of waste generated from the facilities, which iscomposed of slurry and adsorption material, has been stored in the HIC.
Regarding the processing and disposal of radioactive waste, R&D is conducted from four
viewpoints: Identifying Properties; Study on Long-Term Storage Method; Study on Processing of Waste; and Study on Disposal of Waste.
Especially in the case of “Identifying Properties”, “Study on Processing of Waste” and“Study on Disposal of Waste”, sharing the R&D results for mutual benefit is importantto provide feedback for each development project for the purpose of optimisation. At thecore of this research is a ‘Waste Stream’, which refers to the waste management process,from generating and storing to processing and disposal of the waste.
Contaminated radionuclides, such as rubble sampled at the Fukushima Dai-ichi Nuclear
Power Station, were analysed as Identifying Properties. As we evaluate the correlation
between Cs-137, which is a main contaminated radionuclide, and other radionuclides,
Co-60 and Sr-90, we expect to find a correlation with Cs-137. As for the actinoids
nuclides, although a level of 10-3 Bq/g was detected in the rubble samples collected on
the first floor of the reactor buildings at Unit 1 and Unit 3, it is not possible to make any
judgements on a correlation with Cs-137 at this time.
Moreover, actinoids nuclides with 10 Bq/cm2 level were detected in a sample of the floor
surface coat taken from the fifth operating floor of the reactor building of Unit 2. Thissuggests the contamination situation inside the reactor building is possibly different ineach unit, and even in the same unit, it might be different on each floor.
At this stage, apart from Identifying Properties, we are focussing on the following items
and research on them continues: Sorting of Information Regarding the Inventory andCoexistence Substance in Waste, Processing of Waste Generated from Treatment ofContaminated Water and Long-term Storage Measures for the Waste and Prospect of
the Disposal Classification of Each Waste and Establishment of Selection Criteria.

List of References[1] IAEA; Nuclear Power Reactors in the World; IAEA-RDS-2/34; Vienna (Austria) 2014.
[2] Stahl, T.; Strub, E.: Gesellschaft für Anlagen- und Reaktorsicherheit (GRS):
Stilllegung kerntechnischer Anlagen; Köln (Germany) 2012.

[3] VGB PowerTech e.V., Arbeitskreis Abfallmanagement: Entsorgung von Kernkraftwerken;
Essen (Germany) 2011.

[4] Paul, M. et al.: Decommissioning including financial precaution; IAEA joint convention of the safetyof spent fuel management and on the safety of radioactive waste managment 2006; Wien (Austria)
2006.
[5] Noyes, R.: Nuclear waste cleanup technologies and opportunities; 1st edition; New York (USA)1995.
[6] E.ON Kernkraft GmbH (Hrsg.): Kernkraftwerk Würgassen – 12 Jahre erfolgreicher Rückbau;
Hannover (Germany) 2009.

[7] E.ON Kernkraft GmbH (Hrsg.): Vom Kernkraftwerk zur “Grünen Wiese – Stilllegung und Rückbau desKernkraftwerks Würgassen; Hannover (Germany) 2008.

[8] Anthofer, A.; Lippmann, W.; Hurtado, A.: Development and testing of a laser-based
decontamination system.
In: Journal of Optics & Laser Technology 48 (2013); pp. 589-598.

[9] Anthofer, A.; Lippmann, W.; Hurtado, A.: Laser decontamination of epoxy painted concretesurfaces in nuclear plants. In: Journal of Optics & Laser Technology 57 (2014); pp. 119-128.
[10] http://www.world-nuclear.org/info/Country-Profiles/Countries-G-N/Japan/; 25.04.2015.

[11] http://www.world-nuclear.org/info/Country-Profiles/Countries-G-N/Germany/; 11.05.2015.

[12] Brandauer, M.; Gentes, S.; Starflinger, J.: Entwicklung eines Separationsverfahrens zur Behandlungdes Sekundärabfalls der Wasser-Abrasiv-Suspensions-Schneidtechnik; KONTEC15; Dresden(Germany) 2015.
[13] Hess, U.; Grove, T.; Denkena, B.: Definierter Abtrag hochbewehrter Stahlbetonstrukturen;
KONTEC15; Dresden (Germany) 2015.

[14] Sell, H.; Finkenberg, H.: Decontamination of steam generator pipe bundles by means of highpressure water-jets; KONTEC15; Dresden (Germany) 2015.

[15] Kern, P.; Gentes, S.: MANOLA – Vorstellung des Manipulator- und Transportwagensystems;
Jahrestagung Kerntechnik 2012; Berlin (Germany) 2012.

[16] Mende, M. et al.: Environment modeling and path planning for a semi-autonomous manipulator
system for decontamination and release measurement; World Automation Congress (WAC) 2014;
Waikoloa Village (USA) 2014.
[17] Metzger, W.; Held, C.: Liedke, T.: Virtueller Teststand zur Unterstützung des fernhantierten
Rückbaus der Verglasungseinrichtung Karlsruhe (VEK); KONTEC15; Dresden (Germany) 2015.

[18] http://www.iabg.de/en/business-fields/mobility-energy-environment/remotely-operatedhandling-systems-for-nuclear-applications/; 13.05.2015.

[19] Brandt, F.; Schäfer, T.; Claret, F.; Bosbach, D.: Heterogeneous formation of ferric oxide
nanoparticles on chlorite surfaces studied by x-ray absorption spectromicroscopy (STXM); In:
Chemical Geology 329/3 (2012); pp. 42-52.

[20] Becker, U.; Risthaus, P.; Brandt, F.; Bosbach, D.: Thermodynamic properties and crystal growth
behavior of the hashemite (BaSO4–BaCrO4) solid solution; In: Chemical Geology 225 (2006);
pp. 244-255.

[21] Kern P., Gentes S., Notheis S., Mende M., Hein B., Wörn H., MAFRO: Ein semi-autonomes
Manipulatorsystem für die Dekontamination und das Freimessen von Oberflächen; KONTEC 2015:
590-597; 25.-27.03.2015; Dresden, Germany[22] Hentschel S., Börsch F., Gentes S., Feil H., Entwicklung einer automatisierten Wandfräse zum
Dekontaminieren von Betonoberflächen beim Rückbau kerntechnischer Anlagen; KONTEC 2015:
617-622; 25.-27.03.2015; Dresden, Germany[23] Brandauer M., Starflinger J., Gentes S., Physical Separation and Disposal of WAS Secondary Waste
from the Decommissioning of Nuclear Facilities; FILTECH 2015; L14-03 – P085; Köln, Germany31

E ditorial Notes

32

Published by:German Research and Innovation Forum Tokyo (DWIH Tokyo)
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Tel: +81 (3) 5276 8820

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Editorial Team:

Editing: Dr. Anton Philipp Anthofer, Marc Schmittem
Design, layout and lithography: Lisa Eidt
Printed in Japan

ISBN: 978-3-942600-47-7
Tokyo, November 2015

© DWIH Tokyo

The DWIH Tokyo is jointly organized by the German Rectors’ Conference (HRK) and

the German Chamber of Commerce and Industry in Japan. It is funded by the Federal
Foreign Office of Germany and supported by the German Federal Ministry of
Education and Research.

LIST OF CONTRIBUTORS

Dr. Ahmed Abou-El-Ela is Department Head atProfessor Dr. Peter Jehle is Full Professor ofGermany.

Construction Operation at the Technische Univer-

IABG Industrieanlagen-Betriebsgesellschaft mbH,
Dr. Anton Philipp Anthofer is Research Associate

at the Chair of Hydrogen and Nuclear Technology at
the Technische Universität Dresden.

Professor Dr. Dirk Bosbach is Director of the

Nuclear Waste Management and Reactor Safety

Division, Institute of Energy and Climate Research,
at Forschungszentrum Jülich.

Martin Brandauer is Research Associate at theInstitute for Management and Technology inConstruction at Karlsruhe Institute of Technology.
Matthias Finkenberg is Sales Manager at RSTGmbH, Germany.

Jan Hedtstück is Project Manager at Wälischmiller
Engineering GmbH, Germany.

Christian Held is Project Manager at Fuel Reprocessing Plant – Wiederaufarbeitungsanlage Karlsruhe GmbH (WAK), Germany.

Professor Dr. Antonio Hurtado is Director of theInstitute of Power Engineering and Full Professorof Hydrogen and Nuclear Energy at the Technische
Universität Dresden.

Dr. Yukihiro Iguchi is Visiting Professor at the

Research Institute of Nuclear Engineering at the

University of Fukui and Director of the Technology

Development Department, Fugen Decommissioning
Engineering Center, at the Japan Atomic Energy
Agency (JAEA).

Construction Engineering at the Institute ofsität Dresden.

Dr. Marco Klipfel is Project Engineer at Fuel Repro-

cessing Plant – Wiederaufarbeitungsanlage Karlsruhe GmbH (WAK), Germany.

Dr. Guido Kremer is Senior Engineer at IABG Indus-

trieanlagen-Betriebsgesellschaft mbH, Germany.
Yasuaki Miyamoto is Deputy General Manager

at the International Research Institute for Nuclear

Decommissioning (IRID) and Senior Principal Engineer at the Japan Atomic Energy Agency (JAEA).

Kiyoshi Oikawa is Director of the International

Research Institute for Nuclear Decommissioning(IRID).

Dr. Steffen Pankow is member of the Nuclear

Dismantling and Decommissioning division at E.ON
Technologies GmbH, Germany.

Andreas Roth is Managing Director of AMR German
Product & Services GmbH /ANT Applied New Technologies AG, Germany.

Professor Dr. Peter Sahre is Director of VKTA Radiation Protection, Analytics & Disposal Rossendorf
Inc.

Professor Dr. Masayoshi Uno is Vice-Director of

the Research Institute of Nuclear Engineering at the
University of Fukui.

Dr. Michael Weigl is Programme Manager at the

Project Management Agency Karlsruhe of the Karlsruhe Institute of Technology.

Professor Dr. Hajimu Yamana is Vice-Presidentof the Nuclear Damage Compensation and Decommissioning Facilitation Corporation and Professor

Emeritus at the Research Reactor Institute at Kyoto
University.

Professor Dr. Satoshi Yanagihara is professor of
Nuclear Decommissioning and Radioactive Waste

Management at the Graduate School of Engineeringand the Research Institute of Nuclear Engineering of
the University of Fukui.

German Research and Innovation Forum Tokyo

The German Research and Innovation Forum Tokyo (DWIH Tokyo) acts as an umbrella

body for German scientific and research interests in Japan, representing both German

research organisations and innovative companies, thereby strengthening scientific andeconomic cooperation with Japanese partners. The DWIH Tokyo has been set up jointly by
the German Rectors’ Conference and the German Chamber of Commerce and Industry inJapan and is financially supported by the German Federal Foreign Office.
www.dwih-tokyo.jp

Technische Universität Dresden

The Technische Universität Dresden (TUD) is one of eleven German universities that wereidentified as an “excellence university”. TUD has about 37,000 students, 4,400 publicly
funded staff members – among them over 500 professors – and approximately 3,500

externally funded staff members, and is therefore the largest university in Saxony today.
The Chair of Hydrogen and Nuclear Energy is part of the Institute of Power Engineering

at the Faculty of Mechanical Science and Engineering. The research and teaching content
is based on an understanding that there is a national and international demand forpreserving and enhancing competence in nuclear technology to guarantee the safety of
nuclear reactors today and in the future.
tu-dresden.de/enand cultural activities which promotes education and research in science and technology
in order to improve the wellbeing of the people. U Fukui has played a role of regional

centre of nuclear technology, since there are 14 nuclear power plants in the prefecture
where the university is located. It is also contributing to education and technology
development on nuclear decommissioning issues from an academic standpoint.
www.u-fukui.ac.jp/eng

Japanese-German Center Berlin

The Japanese-German Center Berlin (JDZB) is a foundation under German private law andis supported by the Ministry of Foreign Affairs (Japan), the Foreign Office (Germany) andthe state of Berlin. It was founded in 1985. Its task is to promote and deepen JapaneseGerman and international cooperation in the field of science and culture; in particularby supporting German-Japanese mutual understanding at all levels of economic life toimprove cooperation in science, research and culture. To accomplish this task it pursues
conferences and exchange programs and some cultural activities.
www.jdzb.de/en

German-Japanese Symposium on Decommissioning of Nuclear Facilities

Since its foundation in 1949, the University of Fukui has served as a centre of academic

21 April 2015 | Osaka, Japan

University of Fukui