[en] Some aspects of environmental monitoring in the event of radioactivity release from nuclear power stations are discussed, particularly the importance of decisions to be made from the data. Changes which have taken place in the method of air monitoring are described. Programmes FISP and WEERIE used by CEGB in the UK showed up some limitations in monitoring equipment and indicated that ¹³¹I is not always the most hazardous nuclide. The current system puts greater reliance on rapid analysis of samples at the laboratories associated with each power station using multi-channel analyzers and takes a gross beta/gamma count using a shielded BPH probe, rather than a ¹³¹I count. The derivation of a new emergency reference level, on which action such as decision to evacuate is based, is described. The problem of lack of speed of analysis with the microanalyser has been solved by use of the code WEERIE to identify key nuclides. (U.K.)

[en] This paper summarizes the recent use of the Oregon State University TRIGA Reactor (OSTR) for education and training. In particular, data covering the last 5 yr are presented, which cover education through formal university classes, theses, public information, and school programs. Training is covered by presenting data on domestic and foreign reactor operator training, health physics training, and neutron activation analysis training. While education and training only occupy ∼16% of the OSTR's total use time, nevertheless, this is an important mission of all nonpower reactors that cannot be performed effectively in any other way

[en] The presentation discusses the authoritative functions and the departments of the IAEA, especially the Department of Nuclear Safety and Security and its Safety and Security of Radiation Sources Unit. IAEA safety series and IAEA safety standards series inform about international standards, provide underlying principles, specify obligations and responsibilities and give recommendations to support requirements. Other IAEA relevant publications comprise safety reports, technical documents (TECDOCs), conferences and symposium papers series and accident reports. Impacts of loss of source control is discussed, definitions of orphan sources and vulnerable sources is given. Accidents with orphan sources, radiological accidents statistic (1944-2000) and its consequences are discussed. These incidents lead to development of the IAEA guidance. The IAEA's action plan for the safety of radiation sources and the security of radioactive material was approved by the IAEA Board of Governors and the General Conference in September 1999. This led to the 'Categorization of Radiation Sources' and the 'Code of Conduct on the Safety and Security of Radioactive Sources'. After 0911 the IAEA developed a nuclear security plan of activities including physical protection of nuclear material and nuclear facilities, detection of malicious activities involving nuclear and other radioactive materials, state systems for nuclear material accountancy and control, security of radioactive material other than nuclear material, assessment of safety and security related vulnerability of nuclear facilities, response to malicious acts, or threats thereof, adherence to and implementation of international agreements, guidelines and recommendations and nuclear security co-ordination and information management. The remediation of past problems comprised collection and disposal of known disused sources, securing vulnerable sources and especially high-risk sources (Tripartite initiative), searching for, recovering and disposal of orphan or vulnerable sources. Future problems should be prevented by legal and regulatory infrastructure, code of conduct, strengthening or regaining control with a national strategy, increasing security of sources and legal and regulatory controls. The code of conduct on safety and security of radioactive sources is a high level document to governments and regulatory authorities to serve as 'guidance for the development and harmonization of policies, laws and regulations on the safety and security of radioactive sources'; over 60 countries, G8 and EU have endorsed the Code. Its objective is to achieve and maintain a high level of safety and security of radioactive sources and to prevent the malicious use of radioactive sources to cause harm to individuals, society or the environment through the development, harmonization and enforcement of national policies, laws and regulations, and through the fostering of international co-operation. The Code focuses on sealed, high-risk radioactive sources, defined in the IAEA Categorization of Radioactive Sources, TECDOC-1344; it excludes nuclear materials, as defined in the Convention on Physical Protection of Nuclear Materials and excludes radioactive sources within the military or defence programs. The TECDOC 1388 helps strengthening control over radioactive sources in authorized use and regaining control over orphan sources. The IAEA has developed interim guidance on source security, TECDOC-1355, which provides methodologies and includes measures to deter, detect and delay theft

[en] As a result of several requests from reactor users, it was recently decided to install a new cadmium-lined in-core irradiation tube (CLICIT) in the Oregon State University TRIGA Reactor (OSTR). As the title implies, this paper will describe the complete sequence of this process, from the design, and design constraints through manufacture to the actual use of the tube. The design is such that it offers a significant degree of flexibility in use, while still strictly adhering to ALARA concepts. In order to keep costs down, the facility was designed, installed and commissioned by the Oregon State University TRIGA Reactor (OSTR) staff and fabricated locally. As this facility is relatively cheap (about $2,000), and will fit all non-conversion TRIGAs other reactor owners may be interested in copying the OSTR tube design. (author)

No abstract available

[en] A general discussion of what is termed computer assisted learning is first given. This is followed by an account of the work of the National Development Programme in Computer Assisted Learning (NDPCAL) set up in 1973. This includes the use of a PDP 11/40 computer, and nuclear engineering at present has the largest number of teaching programs, a list of which is given. (U.K.)

[en] The purpose of this work is to characterize the types and magnitudes of the potential radiological hazards associated with worst-case transportation accidents involving radioactive material shipments that are typically transported along Oregon highways. The results of this study are now being incorporated into a protective action guide for use by emergency responders. This guide bases the protective actions on the available, observable data and flowcharts, which use the worst-case assumptions for unknown data

[en] The Monte Carlo Neutron/Photon (MCNP) code has been used to perform the neutronics analysis required to support revision of the Oregon State University TRIGA Reactor (OSTR) Safety Analysis Report (SAR). The SAR revision is a necessary part of the preparation of the application for authorization to convert the OSTR core from High Enriched Uranium (HEU) FLIP fuel to a Low Enriched Uranium (LEU) fuel. Before MCNP was applied to LEU-fueled cores, it was first validated by comparing MCNP calculations on FLIP cores to historical, measured values for these cores. The LEU fuel considered was the 20 wt%, 20 % enriched (20/20) TRIGA fuel approved by the Nuclear Regulatory Commission (NRC) in NUREG 1282. The results show that the 20/20 fuel is much more reactive than FLIP fuel. A just-critical OSTR FLIP core contains 65 elements, while a just-critical 20/20 core only needs 51 elements. Similarly, the current operational FLIP core consists of 88 elements, whereas a 20/20 core giving the same core excess only requires 65 elements. This presents a significant problem for the OSTR because of potentially significant neutron flux loss in experimental facilities. Further analysis shows that to achieve a full size operational core of about 90 LEU elements the erbium content of the LEU fuel would need to be increased from 0.47 wt% to about 0.85 wt%. (author)

[en] A research reactor is a core facility in many nuclear research centres (NRCs) of Member States and it is logical that it should be the focus of any international collaboration between such centres. There are several large and sophisticated research reactors in operation in both developed and developing Member States, such as Belgium, China, Egypt, France, Hungary, Indonesia, India, Japan, ROK, Netherlands, South Africa and the USA. There are also several new, large reactors under construction or being planned such as those in Australia, Canada, China, France, Germany, and Thailand. It is felt that the utilization of these reactors can be enhanced by international co-operation to achieve common goals in research and applications. (author)

[en] The development of new physical security regulations has made it desirable for several research reactor facilities to maintain their fuel above the self-protecting level of 100 rem/hr at three feet in the air. Routine verification of this self-protecting status could give rise to appreciable personnel doses. In order to reduce these doses, OSU has developed a self-protection program which utilizes a computer code, and quarterly underwater dose rate measurements. It is estimated that the use of this program has resulted in a dose reduction of up to 5 person rem per year