Winfrith: Life After Decommissioning — Nuclear Site to Science and Technology Park

2003 ◽  
Author(s):  
Alan Neal
Keyword(s):  
Research And Development ◽  
Nuclear Power ◽  
High Efficiency ◽  
Nuclear Reactors ◽  
Nuclear Research ◽  
Environmental Research ◽  
Nuclear Facilities ◽  
Local Council ◽  
Heavy Water Reactor ◽  
The Uk

UKAEA’s Winfrith site was built in the late 1950’s to undertake research and development into electricity generation from nuclear power. Pioneering scientific and technical work was carried out which resulted in a better understanding of nuclear issues, particularly nuclear safety. At its peak, Winfrith employed 2000 staff and at one time had nine operational nuclear reactors. The most noticeable landmark being the Steam Generating heavy Water Reactor (SGHWR) which, when in operation, provided the National Grid with enough electricity for a small town. In the early 1990’s the UK Government wound down its programme of nuclear R&D, and work started on restoring the environment of the Winfrith site by the progressive removal of the nuclear facilities. Winfrith has always been considered to be one of three key sites in Dorset for development of quality employment, and the site management, with the support of the DTI, decided to undertake a programme of environmental restoration that retained appropriate buildings and infrastructure systems that could be put to alternative long term use. To date, successes have been achieved in both the decommissioning work and also the establishment of tenants. All the fuel has been removed from the nuclear reactors and five reactors have been completely dismantled. Decontamination of other facilities has been completed. A notable example of this work is the return of a fuel fabrication building to a green field site. Another example was the decommissioning of a building that contained gloveboxes, and laboratories equipped with high efficiency filtered ventilation systems. This building was decommissioned, the area of land containing it delicensed, and the building leased to non-nuclear tenants. This thorough, painstaking process involved the use of recently developed industry techniques and required close working with the Nuclear Installations Inspectorate (NII). The tenant base is growing and at the end of 2002 there are 40 different companies resident on site with employee numbers ranging from 1 to several hundreds with a total of ∼ 1000 staff. In addition, the UKAEA programme employs ∼ 500 as staff and contractors. The larger tenants include QinetiQ and DSTL (both from the former Defence Evaluation and Research Agency), the Natural Environment Research Council’s Centre for Ecology and Hydrology, and RWE Nukem. The progressive decommissioning work continues and as UKAEA retreats across the site, from east to west, the non-nuclear research and development businesses move in. The range of work established at Winfrith provides a focus for its further development as a scientific and technical centre of excellence. Facilities have been created in partnership with the local council for small and start-up businesses, while strong links are being encouraged with universities that have an interest in areas such as environmental research. Together they will form a vital part of the commercial community, stimulating growth through technical interaction and innovation.

The organisation & the costs of the decommissioning nuclear plants in the UK

2009 ◽  
pp. 63-82
Author(s):  
Steve Thomas
Keyword(s):  
Key Words ◽  
Nuclear Power ◽  
Nuclear Fuels ◽  
Nuclear Facilities ◽  
Nuclear Decommissioning ◽  
Nuclear Plants ◽  
New Public ◽  
Public Body ◽  
The Uk ◽  
Jel Classifications

- UK electricity consumers have paid provisions for decommissioning since before 1980 but by 2002, there were still negligible funds available to pay for decommissioning civil nuclear facilities. By then, the two major UK nuclear companies, British Energy and British Nuclear Fuels Limited (BNFL), were both effectively bankrupt. This paper examines: the pre-2002 provisions for decommissioning and how they were lost; the Nuclear Decommissioning Authority, a new public body which took over ownership of BNFL's facilities including the duty to manage their decommissioning and how it expects to carry out and fund decommissioning of its sites; how the re-launched British Energy will contribute to decommissioning its eight plants; and government plans for collecting decommissioning provisions for any new plants.JEL classifications: L50, L38, H23, H44, L71Key words: Nuclear power, decommissioning cost, funding and polluter pays.

Sellafield Decommissioning Programme: Progress Update

2003 ◽  
Author(s):  
S. F. Challinor
Keyword(s):  
Research And Development ◽  
Fuel Cycle ◽  
Step Change ◽  
Nuclear Facilities ◽  
Extensive Experience ◽  
Strategic Direction ◽  
Wide Range ◽  
Uk Government ◽  
The Uk

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.

Pseudo-Capacitor Structure for Direct Nuclear Energy Conversion

2008 ◽  
Vol 1100 ◽  
Author(s):  
Liviu Popa-Simil
Keyword(s):  
Energy Conversion ◽  
Nuclear Power ◽  
Nuclear Energy ◽  
Nuclear Reactor ◽  
High Efficiency ◽  
Nuclear Reactors ◽  
Direct Conversion ◽  
Space Applications ◽  
Power Sources ◽  
Conversion Efficiencies

AbstractThe advanced space missions need for more power opened the way for advanced nuclear reactors and for alternative power conversion procedures. The most advanced power systems available in space are the fuel cells and nuclear reactors. Both systems manifest low efficiencies for converting the primary energy into electricity and as consequence are requiring high heat dump into space mainly by infrared radiation. The thermo-nuclear power generator also requires a high temperature gas turbine and a mechano-electric generator, finally driving to low conversion efficiencies. The new nano-materials offer the possibility of creating direct energy conversion devices able of achieving high conversion efficiencies up to 99% in the cryogenic versions. The interest for direct conversion of the nuclear energy into electricity appeared in early 1940th, by the invention of the thermo-ionic fission device by Linder. Then a series of patents and scientific papers improved gradually the designs and performances of the devices, up to the actual concepts of beta-voltaic and liquid-electronics. The most intuitive direct conversion device looks mainly like a super mirror- or a heterogeneous super-capacitor. The issues on its operation are related to global conversion efficiencies and the stable operation life-time in high radiation field. There are combinations of nano-structures and actinides assuring both the neutron flux stability, by meeting criticality conditions and the direct conversion or the nuclear energy into electricity. Achieving a high efficiency internal conversion of the nuclear energy into electricity is not enough if it is not completed by a high efficiency power extraction system from the nuclear reactor core into the outside load. The development of the new MEMS devices and micro electronics in the 40 nm technologies provides an excellent background for the production of the electric power harvesting and conversion devices embedded in the fuel. The new nano-structured materials may be produced as radiation energy harvesting tiles that are free of actinides, using them for harvesting the energy of radioactive sources and controlled fusion devices, or may include actinides in their structure achieving critical or sub-critical accelerator driven nuclear reactor assemblies. Another predictable advantage of the nano-structure is the property of self-repairing and self-organizing to compensate the radiation damage and improve the lifetime. Due to direct conversion the power density of the new materials may increase from the actual average of 0.2 kw/cm3 to about 1 kw/mm3 driving to miniaturization of nuclear power sources and reductions of the shield weight. At these dimensions and power densities of few thousands horse power per liter the nuclear power source becomes suitable for mobile applications as powering trains, strategic airplanes, etc. These new developments may drive to the production of high power solid-state compact nuclear battery for space applications, leading to a new development stage.

Decommissioning of Obsolete Nuclear Facilities in the Nuclear Research Institute Rez

2011 ◽  
Author(s):  
Josef Podlaha ◽  
Karel Svoboda ◽  
Eduard Hansli´k
Keyword(s):  
Czech Republic ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Research ◽  
Current Status ◽  
Joint Stock Company ◽  
Nuclear Facilities ◽  
Nuclear Research Institute ◽  
The Czech Republic ◽  
Research Institute

After more than 55 years of activities of the Nuclear Research Institute Rez (NRI) in the nuclear field, there are some obsolete nuclear facilities that shall be decommissioned. NRI is a leading institution in all areas of nuclear R&D in the Czech Republic. NRI has had a dominant position in the nuclear programme since it was established in 1955 as a state-owned research organization and it has developed to its current status. In December 1992, NRI has been transformed into a joint-stock company. The Institute’s activity encompasses nuclear physics, chemistry, nuclear power, experiments at the research reactor and many other topics. Main issues addressed in NRI in the past decades were concentrated on research, development and services provided to the nuclear power plants operating VVER reactors, development of chemical technologies for fuel cycle and irradiation services to research and development in the industrial sector, agriculture, food processing and medicine. The NRI operates two research nuclear reactors, many facilities as a hot cell facility, research laboratories, technology for radioactive waste (RAW) management, radionuclide irradiators, an electron accelerator, etc. The obsolete facilities to be decommissioned comprise various research facilities and facilities for RAW management. Decommissioning of nuclear facilities NRI is the only ongoing decommissioning project in the Czech Republic. Decommissioning started in 2003 and will be finished in 2014. Some facilities have already been successfully decommissioned.

Global Radioxenon Emission Inventory from Nuclear Research Reactors

2021 ◽  
Author(s):  
Martin B. Kalinowski ◽  
Pouneh Tayyebi ◽  
Michael Lechermann ◽  
Halit Tatlisu
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Emission Inventory ◽  
Noble Gas ◽  
Nuclear Research ◽  
Radioactive Isotopes ◽  
Nuclear Facilities ◽  
Research Reactors ◽  
Underground Nuclear Explosions ◽  
Nuclear Explosions

AbstractTo monitor compliance with the Comprehensive Nuclear-Test-Ban Treaty (CTBT), the International Monitoring System (IMS) is being established which will include 40 sensor systems for atmospheric xenon radioactivity. Radioactive isotopes of the noble gas xenon provide the most likely observable radioactive signatures of underground nuclear explosions. These isotopes are frequently detected by IMS noble gas systems as a result of normal operational releases from different types of nuclear facilities including nuclear power plants (NPPs), medical isotope production facilities (MIPFs), and nuclear research reactors (NRRs). Improved knowledge of the contribution of different emission sources on IMS observations strengthens the screening of radioxenon measurements to exclude observations not relevant to emissions from a nuclear explosion. The contribution of NPPs and MIPFs to the global radioxenon emission inventory is fairly well understood. NRRs have yet to be systematically assessed. This paper is the first attempt to assess the total emission inventory of NRRs expressed as annual total discharges. The results can enhance understanding of those sources most likely to impact IMS background observations and to guide future studies on contributions to IMS station background.

Data-based kernel density equations for probability distributions of releases of CTBT-relevant radioxenon isotopes from nuclear facilities and when arriving at IMS stations after atmospheric transport

2021 ◽  
Author(s):  
Martin Kalinowski ◽  
Boxue Liu
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Explosion ◽  
Atmospheric Transport ◽  
Isotopic Ratio ◽  
Probability Distributions ◽  
Kernel Density ◽  
Nuclear Research ◽  
Nuclear Facilities ◽  
Data Set

<p>For the International Monitoring System (IMS) to be effective, it is vital that nuclear explosion signals can be distinguished from natural and man-made radioactivity in the atmosphere. The International Data Centre (IDC) of the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO) applies standard event screening criteria, with the objective of characterizing, highlighting, and thereby screening out, events considered to be consistent with natural phenomena or non-nuclear explosive, man-made phenomena. The objective of this study is to apply the kernel density (KD) approach to generate and investigate probability distributions of isotopic ratios for radioxenon releases from certain types of sources. The goal is to create probability density functions that could be applied e.g. with a Bayesian method to determine the probability whether an IMS observation can be explained by known sources or could possibly be caused by a nuclear explosion. KD equations for nuclear facility releases are derived from the data set of the radioxenon emission inventory of all nuclear power plants and all nuclear research reactors, as well as selected medical isotope production facilities in the calendar year 2014. For all types of sources, KD equations will be linked with isotopic ratio calculations that connect the sources and IMS stations as receiver.</p>

scholarly journals Anthropogenic Radiocarbon: Past, Present, and Future

Radiocarbon ◽  
1986 ◽  
Vol 28 (2A) ◽  
pp. 668-672 ◽  
Author(s):  
Pavel Povinec ◽  
Martin Chudý ◽  
Alexander Šivo
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Reactor ◽  
Nuclear Reactors ◽  
Pressurized Water Reactors ◽  
Anthropogenic Radionuclides ◽  
Pressurized Water ◽  
Heavy Water Reactor ◽  
Weapon Testing ◽  
Water Reactors

14C is one of the most important anthropogenic radionuclides released to the environment by human activities. Weapon testing raised the 14C concentration in the atmosphere and biosphere to +100% above the natural level. This excess of atmospheric C at present decreases with a half-life of ca 7 years. Recently, a new source of artificially produced 14C in nuclear reactors has become important. Since 1967, the Bratislava 14C laboratory has been measuring 14C in atmospheric 14CO2 and in a variety of biospheric samples in densely populated areas and in areas close to nuclear power plants. We have been able to identify a heavy-water reactor and the pressurized water reactors as sources of anthropogenic 14C. 14C concentrations show typical seasonal variations. These data are supported by measurements of 3H and 85Kr in the same locations. Results of calculations of future levels of anthropogenic 14C in the environment due to increasing nuclear reactor installations are presented.

Spanish Approach to Large Decommissioning Projects

2011 ◽  
Author(s):  
Juan Luis Santiago ◽  
Alejandro Rodri´guez
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Nuclear Research ◽  
Lessons Learned ◽  
Research Centre ◽  
Nuclear Facilities ◽  
Material Management ◽  
Site Remediation ◽  
Key Aspects

The Spanish experience related to the decommissioning of nuclear facilities includes the decommissioning of the Vandello´s I Nuclear Power Plant, the decommissioning of the CIEMAT Nuclear Research Centre and the decommissioning of the Jose´ Cabrera Nuclear Power Plant. This paper reviews the key aspects of these projects and describes the lessons learned related to preparatory activities, auxiliary facilities, decommissioning technologies, material management and site remediation and release.

Using Probabilistic Criteria in an Assessment of the Potential Radiological Consequences of the Decommissioning of a Nuclear Research Reactor

2013 ◽  
Author(s):  
Christian Wallner ◽  
Anna-Maria Rall ◽  
Severin Thummerer
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Research Reactor ◽  
Nuclear Research ◽  
Exposure Dose ◽  
Occurrence Frequency ◽  
Normal Operation ◽  
Nuclear Facilities ◽  
Nuclear Research Reactor

In order to assess the risk of radiological consequences of incidents and accidents in nuclear facilities it is important to contemplate their frequency of occurrence. It has to be shown that incidents and accidents occur sufficiently seldom according to their radiological consequences i. e. the occurrence frequency of radiological doses has to be limited. This is even demanded by the German radiation protection ordinance (StrlSchV), which says that in nuclear facilities other than nuclear power plants (NPP) in operation and for decommissioning, the occurrence frequency of incidents and accidents shall be contemplated in order to prove the design of safety measures and safety installations. Based on the ideas of the ICRP64, we developed a risk based assessment concept for nuclear facilities, which fulfils the requirements of the German regulations concerning dose limits in normal operation and design basis accidents. The general use of the concept is dedicated to nuclear facilities other than nuclear power plants (NPP) in operation and for decommissioning, where the regulation of risk assessment is less sophisticated. The concept specifies occurrence frequency limits for radiation exposure dose ranges, i. e. the occurrence frequency of incidents and accidents has to be limited according to their radiological effects. To apply this concept, scenarios of incidents and accidents are grouped in exposition classes according to their resulting potential effective dose to members of the general public. The occurrence frequencies of the incidents and accidents are summarized in each exposition class whereas the sum must not exceed the frequency limits mentioned above. In the following we introduce the application of this concept in the assessment of the potential radiological consequences of the decommissioning of a nuclear research reactor. We carried out this assessment for the licensing process of the decommissioning on behalf of German authorities.

Chinese Attitudes Towards Nuclear Weapons, 1964–9

1972 ◽  
Vol 50 ◽  
pp. 244-271
Author(s):  
Jonathan D. Pollack
Keyword(s):  
Research And Development ◽  
Nuclear Power ◽  
Gross National Product ◽  
Nuclear Research ◽  
Ballistic Missile ◽  
The Pacific ◽  
20Th Anniversary ◽  
Technical Manpower ◽  
Near Future ◽  
Technological Achievement

10 1969 was not only the 20th anniversary of the founding of the Chinese People's Republic (C.P.R.); it also marked the culmination of China's fifth year as a nuclear power. During this five-year period there were 10 detonations, three of which were thermonuclear and one of which was tested underground. At least one of the warheads was fired from a guided missile. According to one estimate, current defence expenditures amount to 10 per cent. of China's gross national product, and one-fifth of this outlay is devoted to nuclear research and development alone. A large portion of China's advanced scientific and technical manpower has also been assigned to this field. Although an adequate delivery system for this limited nuclear capability, as of November 1971, is not known to be operational, China's progress in the research and development of advanced weapons has clearly been substantial. The launching of Chinese satellites in 1970 and 1971 and the likelihood of an intercontinental ballistic missile (ICBM) test in the near future are further evidence of major technological achievement. Peking's entry, then, into the “nuclear club” has been a major concern of China's leaders; it has also had significant consequences for American defence planners. The explicit rationale for the Nixon Administration's expansion of the anti-ballistic missile (ABM) system in early 1970, for example, was to guard against the possibility of a Chinese attack in the 1980s and thus to assure the reliability of American defence commitments in East Asia and the Pacific.

Sign in / Sign up

Export Citation Format

Share Document