scholarly journals IN-PILE INSTRUMENTATION TO SUPPORT FUEL CYCLE RESEARCH AND DEVELOPMENT - FY12 STATUS REPORT

2012 ◽  
Author(s):  
J. . Rempe ◽  
J. Daw ◽  
D. Knudson ◽  
R. Schley
Author(s):  
S. F. Challinor

In 1999 the UK government announced a step change in the strategy for the delivery of the UK civil nuclear clean-up programme. BNFL has responded to the Governments announcement by changing the strategic direction and increasing the priority on remediation activities across the Company. BNFL has extensive experience in decommissioning nuclear facilities having undertaken remediation and decommissioning operations on BNFL sites for many years, encompassing a wide range of projects including reactors, fuel cycle plants and Research and Development facilities. This paper describes the challenges posed by, and the progress made, on some of the range of decommissioning projects undertaken on the Sellafield site as part of its decommissioning and remediation portfolio. These decommissioning operations cover a variety of redundant fuel cycle facilities ranging in size and complexity in both beta gamma and alpha contamination environments utilising manual and remote decommissioning techniques to systematically and progressively reduce the hazard on the site.


Author(s):  
Fumihiko Kanayama

The Japan Atomic Energy Research Institute Reprocessing Test Facility (JRTF) was the first reprocessing facility which was constructed by applying only Japanese technology to establish basic technology on wet reprocessing. JRTF had been operated since 1968 to 1969 using spent fuels (uranium metal/aluminum clad, about 600kg as uranium metal and 600MWD/T) from the Japan Research Reactor No.3 (JRR-3). Reprocessing testings on PUREX process were implemented at 3 runs, so that, 200g of plutonium dioxide were extracted. After JRTF was shut down at 1970, it had been used for research and development of reprocessing since 1971. The more mature research and development of nuclear are, the more opportunity of dismantling of old nuclear facilities would be. Japan Atomic Energy Agency (JAEA) has an experience of full scale of dismantling through decommissioning of Japan Power Demonstration Reactor (JPDR)1). On the other hand, we didn’t have that of fuel cycle facility. Moreover, it is considered that dismantling methods of nuclear reactor and fuel cycle facility are different for following reason, components contaminated TRU nuclide including Pu, and components installed inside narrow cells. Dismantling methods are important factor to decide manpower and time for dismantling. So, it is indispensable to optimize dismantling method in order to minimize manpower and time for dismantling. Considering the background mentioned above, the decommissioning project of JRTF was started in 1990. The decommissioning project of JRTF is carried out phase by phase. Phase 1; Investigation for dismantling of the JRTF2)3)4). Phase 2; R&D of decommissioning technologies for dismantling of the JRTF5)6)7)8). Phase 3; Actual dismantling of the JRTF9)10). There were several components used for reprocessing and a system for liquid radwaste storage, and those were installed inside of each of several thick concrete cells. The inner surfaces of each cell were contaminated by TRU nuclides including Pu. In phase 3, components used in reprocessing and a system for liquid radwaste storage were dismantled. Moreover, opening was made in concrete walls (including ceiling) for this work. Effective practices for dismantling fuel cycle facilities were obtained through these works. On this report, effective dismantle methods obtained by actual dismantling activities in JRTF are introduced.


Author(s):  
A. J. H. Donné

The European roadmap to the realization of fusion electricity breaks the quest into eight missions. For each mission, it reviews the current status of research, identifies open issues, and proposes a research and development programme. ITER is the key facility on the roadmap as it is expected to achieve most of the important milestones on the path to fusion power. The Fusion Roadmap is tightly connected to the ITER schedule and the vast majority of resources in fusion research are presently dedicated to ITER and its accompanying experiments. Parallel to the ITER exploitation in the 2030s, the construction of the demonstration power plant DEMO needs to be prepared. DEMO will for the first time supply fusion electricity to the grid and it will have a self-sufficient fuel cycle. The design, construction and operation of DEMO require full involvement of industry to ensure that, after a successful DEMO operation, industry can take responsibility for commercial fusion power. The European fusion roadmap provides a coherent path towards the fusion power plant, and it proposes in an integrated way to find solutions for all challenges that still need to be addressed. This article is part of a discussion meeting issue ‘Fusion energy using tokamaks: can development be accelerated?’


Sign in / Sign up

Export Citation Format

Share Document