following paper attempts to describe the high level of sophistication incorporated in the SP100 design, and the high degree of technology readiness at the time of programmediscontinuation.

04/01304 The dynamic analysis of nuclear waste cask under impact loading Teng, T. L. et al. Annals of Nuclear Energy, 2003, 30, (14), 1473-1485. Nuclear waste is sealed in steel casks and transported through the public domain to disposal sites. The casks are designed primarily to transport and store 30-55 gallon drums of waste. The casks meet safety requirements that govern how they respond to an accidental drop onto rigid ground. In this paper, a finite element method was used to perform impact analysis on a cask. The calculation simulates the deformation of a 55-gallon cask during and after an edge impact form a height of 1.2 m, falling at a 30 ° incline onto rigid ground. The regulations require that the plastic strain at an impact corner must not exceed the yielding strain of the cask material.

04/01305 The influence of oversized solute additions on radiation-induced changes and post-irradiation intergranular stress corrosion cracking behavior in high- purity 316 stainless steels Fournier, L. et al. Journal of Nuclear Materials, 2003, 321, (2-3), 192- 209. The influence of oversized solute additions on the radiation-induced microstructure, radiation-induced segregation (RIS) at grain bound- aries and post-irradiation intergranular stress corrosion cracking (IGSCC) behaviour of model, high-purity 316 stainless alloys, doped with either 0.3 at.% platinum or 0.3 at.% hafnium, and proton- irradiated to 2.5 and 5 dpa at 400°C was examined. Radiation-induced microstructure was characterized using both bright and dark field imaging techniques in transmission electron microscopy. Platinum addition was found to promote void nucleation and to increase both the loop density and the mean loop diameter relative to the base alloy at 2.5 dpa. Addition of hafnium was effective in reducing swelling at 2.5 and 5 dpa. Hafnium addition also significantly decreased the mean loop diameter relative to the base alloy. Both platinum and hafnium additions also resulted in significant suppression of RIS at grain boundaries at 2.5 dpa. At 5 dpa, the influence of hafnium addition on RIS was still beneficial but much less pronounced. Comparative constant elongation rate tensile tests performed in a simulated boiling water reactor environment at 288°C demonstrated a beneficial effect of hafnium addition and to a lesser extent platinum addition on the post- irradiation IGSCC behaviour of 316 stainless steel alloys. The 316SS alloy doped with platinum exhibited a slightly lower susceptibility to post-irradiation IGSCC than the 316SS base alloy at both 2.5 and 5 dpa. Most spectacularly, the 316SS alloy doped with hafnium was found to be not susceptible to post-irradiation IGSCC at both 2.5 and 5 dpa. The mechanisms by which oversized solute additions impact point defect behaviour as well as the links between radiation-induced changes and irradiation-assisted stress corrosion cracking are discussed.

04•01306 The use of fuzzy logic methodology to establish inservice inspection priorities for nuclear components GuimarO_es, A. C. F. Progress in Nuclear Energy, 2003, 42, (3), 311-322. This work describes the use of fuzzy logic methodology to estimate inservice inspection (ISI) priorities for nuclear components with Adaptive Neural Fuzzy Inference system (ANFIS). To estimate ISI priorities for components the methodology uses probabilities of component failures and the core damage frequency of each component failure. The specific systems addressed in this work are the auxiliary feedwater, low-pressure injection, and reactor coolant systems selected from the Surry Nuclear Power Station Unit 1 (Surry-1). For illustration some examples were developed and their results, when compared with reference work lead to important conclusions.

04/01307 The use of virtual reality for preparation and implementation of JET remote handling operations Sanders, S. et al. Fusion Engineering and Design, 2003, 69, (1-4), 157 161. The use of real time 3-D computer graphic models for preparation and support of remote handling operations on JET has been in use since the mid 1980s. A complete review has been undertaken of the functional requirements and benefits of VR for remote handling and a subsequent market survey of the present state-of-the-art of VR systems has resulted in the implementation of a new system for JET. The VR system is used in two discrete modes: in on-line mode the remote handling equipment Electro-mechanical hardware is connected to the VR system and provides input for the VR system to update a real time 3-D display of the equipment inside the torus. This mode supplements the video camera system and assists with camera control and warnings of impending or potential collisions. In off-line mode the operator manipulates the VR system model with no connections to the remote handling equipment. This mode is used during preparation of

05 Nuclear fuels (economics, policy, supplies, forecasts)

RH operational strategies, checking of operational feasibility and operations procedures. Various VR systems were evaluated against a detailed technical specification that covered visualization function and performance, user interface design and base model input/creation capabilities. The cheapest of those systems that satisfied the technical requirements was selected.

04/01308 Transport-burnup code systems and their applications for IAEA ADS benchmark Jiang, X. and Xie, Z. Annals of Nuclear Energy, 2004, 311 (2), 213-225. Recently for transmutation of spent nuclear fuel, the Accelerator Driven System (ADS) is introduced. Because of anisotropic flux distribution caused by the external source, the nuclear calculation of ADS is significantly different from the traditional nuclear reactor. Two sets of transport burnup code systems based on the transport theory: Monte Carlo-burnup code system and transport-burnup code system are developed, and are applied to IAEA ADS benchmark. Initial enrichments of 233U that correspond to given initial K~ff values are calculated. And then, the spatial distributions of power density at BOL, the void reactivity effects, the external source effectiveness, and the evolution curves of Kerr and external source as a function of time are also calculated for every given Keff (BOL). The numerical results are in a good agreement with those of participants.

Economics, policy, supplies, forecasts

04/01309 Analysis of operators' performance under emergencies using a training simulator of the nuclear power plant Park, J. et al. Reliability Engineering & System Safety, 2004, 83, (2), 179 186. It is well known that there are many factors that affect the reliability of nuclear power plants (NPPs). Among them, human reliability has been considered one of the most important factors. Thus, not only in order to quantify human reliability but also to identify main causes that can degrade human reliability, various kinds of human reliability analysis (HRA) methods have been suggested and utilized in many countries. However, to perform HRA more appropriately, it is necessary to collect plant-specific or domain-specific human performance data: especially for emergencies: because they can be used to generate requisite information for HRA. From this point of view, simulator studies under emergencies may be considered important sources for obtaining human performance data. In this study, the performance data of operating crews in coping with emergencies of the reference NPP have been collected and analysed to develop human performance database (HPDB). Since the number of collected records is 112, it can be said that extracted/analysed results included in HPDB are statistically meaningful. Therefore, HPDB can be used not only for HRA input data but also for multiple purposes such as improving emergency operating procedures and developing advanced HRA methods.

04/01310 Feasibility study of iridium production at ETRR-2 Abou-Zaid, A. A. and Nasr, M. Annals of Nuclear Energy, 2004, 31, (1), 87-96, Iridium is a very rare, precious, silvery white, hard, brittle metal that even resists most acids, it is one of the densest substances known on earth 3 (~22.5 g/cm ). The important radioactive isotope (iridium-192) is produced by neutron irradiations of iridium-191 found in natural iridium. Ir-192 has a half-live of 74 days and is used in industrial radiography and it has many other applications. This work presents a neutronic analysis part of a feasibility study of iridium production in the core central position of ETRR-2. A design of iridium irradiation device is proposed. Monte Carlo simulation of the reactor core with and without Iridium device has been performed. The results showed that the reactivity worth of about 120 g is less than 1200 PCM, which agree with the safety limits of the reactor. Also the heat deposition and power peaking factor have been calculated. Finally, the activity of iridium as a function of irradiation time was calculated.

04/01311 Hydrogen production by atomic energy viewed from electric power company Omoto, A. Genshiryoku Eye, 2003, 49, (1), 34-36. (In Japanese) A review of hydrogen as an energy medium, manufacturing and supply technology.

04101312 Japanese site for ITER; Rokkasho Kishimoto, H. Fusion Engineering and Design, 2003, 69, (1-4), 553-561. This paper describes the status of Japanese efforts for hosting 1TER in Japan. In May 2002, Japanese Government decided to propose an ITER site, Rokkasho in Aomori Prefecture, a Northern part of the

Fuel and Energy Abstracts May 2004 179