On capabilities and limitations of current fast neutron-flux monitoring instrumentation for the DEMO LFR ALFRED

Among Gen IV projects for future nuclear power plants, Lead cooled Fast Reactors (LFR) seem to be a very interesting solution due to its benefits in terms of fuel cycle, coolant-safety and waste management. The novelty of the matter causes some open issues about coolant chemical aspect, structural aspects, monitoring instrumentation, etc. Particularly hard neutron flux spectra would make traditional neutron instrumentation unfit to all reactor conditions, i.e. source, intermediate, and power range. Identification of new models of nuclear instrumentation specialized for LFR neutron flux monitoring asks for an accurate evaluation of the environment the sensor will work in. In this study, thermal-hydraulics and chemical conditions for LFR core environment will be assumed, as the neutron flux will be studied extensively by means of the Monte Carlo transport code MCNPX. The core coolant’s high temperature drastically reduces the candidate instrumentation, because only some kind of fission chambers and Self Powered Neutron Detectors can be operated in such an environment. This work aims at evaluating the capabilities of the available instrumentation (usually designed and tailored for Sodium cooled Fast Reactors, SFRs) when exposed to the neutron spectrum derived from ALFRED, a pool-type LFR project to demonstrate the feasibility of this technology into the European framework. This paper shows that such class of instrumentation does follow the power evolution, but is not completely suitable to detect the whole range of reactor power, due to excessive burn-up, damages or gamma interferences. Some improvements are possible in order to increase the signal-to-noise ratio, by optimizing each instrument in the range of reactor power, such to get the best solution. The design of some new detectors are here proposed, together with a possible approach for prototyping and testing them by means of a fast reactor

Fast Traveling-Wave Reactor of the Channel Type

The main aim of this paper is to solve the technological problems of the TWR based on the technical concept described in our priority of invention reference, which makes it impossible, in particular, for the fuel claddings damaging doses of fast neutrons to excess the ~200 dpa limit. Thus the essence of the technical concept is to provide a given neutron flux at the fuel claddings by setting the appropriate speed of the fuel motion relative to the nuclear burning wave. The basic design of the fast uranium-plutonium nuclear traveling-wave reactor with a softened neutron spectrum is developed, which solves the problem of the radiation resistance of the fuel claddings material.Comment: 18 pages, 5 figures, 2 table

Space radiation studies at the White Sands Missile Range Fast Burst Reactor

The operation of the White Sands Missile Range Fast Burst Reactor is discussed. Space radiation studies in radiobiology, dosimetry, and transient radiation effects on electronic systems and components are described. Proposed modifications to increase the capability of the facility are discussed

Potential of Pyrolysis for valuable products obtaining from wheat straw lignin produced by CIMV technology

Two configurations of fast pyrolysis realized in flowing (inert gas flow) and ablative-type reactors were used for phenolic fraction obtaining. The maximum yield of phenolic compounds was achieved at 450 degrees of Celsius in the case of ablative reactor usage (7,6%). Application of catalysts (Na+ and K+) allowed to increase the yield of phenolic compounds up to 8,5%

Selection of alternative central-station technologies for the Satellite Power System (SPS) comparative assessment

An important effort is the Satellite Power System (SPS) comparative Assessment is the selection and characterization of alternative technologies to be compared with the SPS concept. The ground rules, criteria, and screening procedure applied in the selection of those alternative technologies are summarized. The final set of central station alternatives selected for comparison with the SPS concept includes: (1) light water reactor with improved fuel utilization, (2) conventional coal combustion with improved environmental controls, (3) open cycle gas turbine with integral low Btu gasifier, (4) terrestrial photovoltaic, (5) liquid metal fast breeder reactor, and (6) magnetic confinement fusion

The rise and fall of the fast breeder reactor technology in the UK: between engineering “dreams” and economic “realities”?

This report explores the evolution of the fast breeder nuclear reactor programmes in the UK, from the period of great promises and expectations in the 1950s and 1960s towards their progressive abandonment in the 1980s and 1990s. The project, of which this report is an element, aims thereby to draw lessons relevant for the current “nuclear renaissance” and medium-term planning on the future of nuclear power. Given that the fast breeder programmes were closely interlinked with the general evolution of nuclear power in the UK, this report includes a fairly detailed historical description of this more general ‘nuclear context’. This primarily chronological description of the evolution of the UK fast breeder programmes provides a basis for a comparison between the evolution of the British and French fast breeder reactor programmes. A central question in such a comparison concerns the lateness of the abandonment of the fast breeder programme in France, as compared to most other countries developing this technology. The cross-country comparison will explore the relative influence of the contextual and historical conditions within which the nuclear technologies have evolved in France and the UK on the one hand, and the ‘universal’ factors common to the evolution of socio-technical systems in general on the other. This exploratory research was based on documentary analysis and eleven interviews of experts involved in, or with knowledge of, the UK fast breeder reactor (FBR) programmes

Constitutive Equations for Use in Design Analyses of Long-life Elevated Temperature Components

Design analysis needs and procedures relative to elevated temperature components in liquid metal fast breeder reactor (LMFBR) system were examined. The effects of the thermal transients on the pressure boundary components are enhanced by the excellent heat transfer properties of the liquid sodium coolant. Design criteria for high temperature nuclear reactor components recognize the potential occurrence of inelastic structural response. Specifically, criteria and limits were developed which reflect a recognition of this potential and employ design by analysis concepts that requires that inelastic (elastic-plastic and creep) analyses be performed. Constitutive equations to represent multiaxial time-dependent responses of LMFBR alloys are established. The development of equations applicable under cyclic loading conditions are outlined