Papers in this volume: 8
1. Effect of irradiation creep strain on the coefficient of thermal expansion of AGL IMI-24 and UCAR GCMB nuclear graphite moderator bricks
Author(s): Carter D.A.J.
Page: 21
Keywords: Advanced gas-cooled reactors (AGRs), Creep, Reactor, Thermal expansion
Abstract: British Energy Ltd (BE) operates all seven twin advanced gas-cooled reactor (AGR) power stations in the UK. In the AGRs, neutrons from the heat-producing process of fuel fission are moderated by graphite, and both graphite and fuel are cooled by pressurised carbon dioxide. The moderation process, together with corrosion by the coolant, alters the material properties of the graphite, which in turn influences the functionality of the moderator core. As a consequence, it is important to BE to understand the behaviour of irradiated graphite. This paper explains that a materials model of how graphite materials properties evolve with increasing dose and fluctuating temperature was developed.
2. Where do we go from here? Reflections on the future of nuclear energy in the United States
Author(s): Colvin J.F.
Page: 25
Keywords: Carbon dioxide, Energy, Environment, Global warming, Nuclear operations and safety, Nuclear power, Production levels, Public opinion, Regulatory issues, United States, US nuclear industry
Abstract: Following a brief look at the US nuclear industry over the past few years, this paper considers current issues and future plans with an emphasis on the role of the Nuclear Energy Institute. It concludes that the nuclear energy industry in the USA is in a stronger position today than at any time in its history. Production levels and safety are at historic highs, and costs are at historic lows, and new plant construction could commence much sooner than previously expected.
3. Facing the challenges of a competitive market
Author(s): Hollins P.
Page: 31
Keywords: British Energy plc (BE), Carbon dioxide, Competition, Energy, Global warming, Nuclear development, Nuclear operations and safety, Nuclear power, United Kingdom
Abstract: British Energy is one of the world's largest nuclear generating companies. This paper describes the business environment in which the company competes, its strategic responses to the challenges it faces, and gives some conclusions regarding the priorities for the nuclear generation industry if it is to thrive as a mainstream source of energy.
4. Lessons learned? Selected public acceptance case studies since Three Mile Island
Author(s): Blee D.
Page: 35
Keywords: Nuclear accidents, Nuclear power, Safety, United States, US nuclear industry
Abstract: This paper will present an overview of the present situation, some recent polling survey information, and then look at lessons learned in terms of selected case studies and some global issues over the 22 years since the Three Mile Island (TMI) accident. That is quite an ambitious topic but there are some important lessons we can learn from the post-TMI era.
5. Progress towards new recommendations from the International Commission on Radiological Protection
Author(s): Clarke R.H.
Page: 39
Keywords: Dose limits, National Radiological Protection Board (NRPB), Radiation monitoring and dose management, Radiological health and safety, Radiological protection, Safety guidelines
Abstract: There has been a hundred-year history of the uses of radiation in medicine and industry. Throughout that time there has also been advice on the need to protect people from the hazards associated with exposure. This paper traces the evolution of protection standards through the differing phases that are identified. These phases reflect changes both in scientific understanding of the biological effects of exposure and of the social and ethical standards to be applied. An analysis is then given of the reasons why the challenges to the International Commission on Radiological Protection (ICRP), especially about the linear non-threshold response model, have arisen. As a result of considering the issues, the Main Commission of ICRP is now consulting on a revised simpler approach which is based on an individual-oriented philosophy and represents a potential shift by the Commission from the past emphasis on societal-oriented criteria. These proposals have been promulgated through the International Radiation Protection Association (IRPA) and an open literature publication was published in the Journal of Radiological Protection in June 1999. On the basis of comments received and the observations presented at the IRPA 10 Conference, the Commission will begin to develop the outline of the next recommendations.
6. Some aspects of Ni behaviour in PWR primary coolant
Author(s): Dickinson W., Henshaw J., Sims H.E. and Garbett K.
Page: 49
Keywords: Chemical processes (including corrosion), Nickel, Pressurised water reactors (PWRs), PWR coolant, Radiolysis, Solubility, Steam generators, Water chemistry
Abstract: Nickel chemistry in a pressurised water reactor (PWR) primary circuit is important both because it can be activated to ?58&/sup;Co and because it is a major constituent of fuel clad deposits in plants affected by axial offset anomalies (AOAs). It has been suggested that a small decrease in the coolant dissolved H2 concentration would switch the stable species from metallic nickel to NiO, which would deposit less as it is more soluble and thus reduce the extent of activation. Furthermore, it has been argued that the presence of NiO rather than metallic nickel in AOA deposits is an indication of oxidising conditions in the core. To understand nickel chemistry in a PWR core, it is necessary to consider not only thermodynamics but also radiation chemistry effects. In addition, some thermal processes may be kinetically constrained. Consequently, a thermodynamic model has been developed to simulate nickel chemistry. This paper discusses the results of thermodynamic and kinetic modelling and suggests that further experimental data are needed.
7. Transuranic waste management at Los Alamos National Laboratory
Author(s): Balkey J.J. and Wieneke R.E.
Page: 55
Keywords: Computerised, Minimisation, Radioactive waste management - transport and disposal, Regulatory issues, Transuranic
Abstract: Los Alamos National Laboratory (LANL) was the first to ship transuranic waste for deep geologic disposal in the waste isolation pilot plant (WIPP) in Carlsbad, New Mexico. This was the culmination of a tremendous effort on the part of personnel at the Plutonium Facility (TA-55) where the waste was generated and of LANL waste management personnel. The Plutonium Facility provides a wide variety of actinide research and development capabilities in support of national defence needs. Many of these operations produce a wide variety of waste forms, including transuranic waste from activities in the glove-box lines throughout the facility. Critical to the success of this shipment was the integrity of the waste management programme at TA-55. A group of dedicated waste management professionals worked intimately with actinide processing operations personnel to assure that all waste packages met the WIPP waste acceptance criteria and were documented and packaged in accordance with all applicable regulations. Records are largely computerised, eliminating paper forms and improving the integrity of data packages and expediting the review and approval process. Research into waste minimisation has succeeded in identifying processes to reduce the volumes of transuranic waste produced and has resulted in the implementation of decontamination and waste avoidance techniques in the facility. This paper provides a broad overview of current waste management activities in the TA-55 Plutonium Facility.
8. Engineering considerations associated with plants used for storage of intermediate-level waste - a regulator's view
Author(s): Seddon W.
Page: 61
Keywords: Intermediate level waste, Public opinion, Radioactive waste management - transport and disposal, Regulatory issues, Retrievable storage, UK regulator's view
Abstract: Everyone associated with the nuclear industry will know that the provision of a deep repository has receded by at least several decades. The question now is%3A �How does the nuclear industry engineer a suitable storage regime for the foreseeable future?�. This paper explores some of the engineering considerations that Nuclear Installations Inspectorate specialist inspectors need to address when considering the safety case for a long-term radioactive materials store. Any licensee contemplating building a store should already know of such items. Integrity of waste form, storage container, handling equipment and store structure are addressed. Licensee's knowledge management is also considered.