Fast Reactor Design

Klueh, R. L., in Proc. Int. Conf. Sodium Technol. Large Fast Reactor Design, Nov. 7-9 1968 ANL-7520, Pt. 1, 171, Argonne National Laboratory Klueh, R. L., Corrosion, 25, 416 (1969)... 

Al. Argonne National Laboratory Proceedings of the International Conference on Sodium Technology and Large Fast Reactor Design, Report AN1 7520, 1968, especially pp. 291-388. 

An examination has been made of how the currently available computing capabilities could be used to reduce Liquid Metal Fast Reactor design, manufacturing, and construction cost. While the examination focused on computer analyses some other promising means to reduce costs were also examined. 

Lead cooled fast reactor design assumes the subassembly with fuel pins arranged in square lattice with large pitch-to-diameter ratio (s/d 1.4-1.5). In LMFR a more tight arrangement of fuel pins is adopted (s/d 1.1-1.18) ... 

The 4S is a new concept of fast reactor designed to meet the goals of nuclear power and offers many attractive advantages. Commercial operation of the 4S is expected to solve a number of problems that humans will encounter in the 21st century. 

Any future fast reactor design should, as a fundamental design criteria, require all sodium systems be provided with an effective sodium removal capability, i.e. draining. In many cases techniques will be simple and inexpensive to implement. In other systems, reactor vessels or steam generators for example techniques will need to be debated. 

New techniques for the removal of sodium, both bulk and residual, should be pursued for both current reactors as well as implemented into any new fast reactor designs. Techniques should address the entire range of possible alternatives, without limitations of currently existing technologies. Potential future in situ techniques should be identified, prioritized and fully developed allowing the decommissioning of fast reactors to be forthright and cost effective. 

Holmes J.A.G. "Developments in UK commercial fast reactor design." Nuclear Energy, Vol 20 no.l. February 1981. 

The TCM on Creep Fatigue Damage Rules to be used in Fast Reactor Design , hosted in the UK in June... 

Accident studies with the European Accident Code (EAC-2) were continued, but at a reduced pace, for the sodium-cooled 800 MWe fast reactor design used in the European WAC benchmark calculation of 1989. 

This appendix provides a brief description of the Fast Flux Test Facility (FFTF) fuel handling system and its operation as described by Cabell (1980) and in the Fast Flux Test Facility System Design Description (FFTF, 1983). The description is limited to those system features that are potentially relevant to the refueling of a liquid-salt very high-temperature reactor (LS-VHTR). Because the FFTF was designed as a reactor to test fuel, it has additional capabilities and equipment compared with a sodium-cooled fast reactor designed only to produce electricity. 

P. Greebler, G. L. Gyorey, B. A. Hutchins, and B. M. Segal, Implications of Recent Fast Critical Experiments on the Basic Fast Reactor Design Data and Calculational Methods. Proc. Intern. Conf. Fast Reactor Experiments and Their Analysis, Oct. 10-13,1966, p. 66. 

The goal is to have a proven fast reactor design available for commercial deployment in the first decades of the next century, when the need for replacement of ageing nuclear power plants arises in Eurqpe. A necessary prerequisite is to have operati(Mial experience from an EFR demonstration plant in advance of commercial deployment To achieve this goal, the EFR programme shown on Figure has been structure into the following main phases. 

On scxiium fire hazards and in-service inspection significant progress has been made with EFR compared to previous fast reactor designs. 

The gas-cooled reactors discussed here are all thermal reactors with a graphite moderator. There has been work on gas-cooled fast reactor designs but these have been generally outside the SMR range. 

Reactor Physics for Plutonlum-Rieled Fast Reactor Design—I... 

Reactor Physics for Plutonlum-Rjeled Fast Reactor Design—If... 

Romano, A J., Wachtel, S. J., and Bdamut, C. J., Proceedings of International Conference on Sodium Technology for Large Fast Reactor Design, ANL-7520, Pt. 1, Atgonne National Laboratoiy, 1968, p. 151. 

The FRDB refleets stages that have led to the physieal and teehnological substantiation of fast reactor designs (from the first multi-purpose demonstration plant BN-350 to the EFR commercial power plant projeet). It eomprises the numerous R D findings that form the basis of fast reactor technology and... 

Summing up, the FRDB attempts to document the knowledge in fast reactor design and technology, as well as to preserve and to disseminate it until sustainability and economics criteria will create the necessary condition for large-scale deployment of fast reactors. 

The recurring themes are the selection and summary of the data associated with the choice of coolant, feel and structural materials, reduction of the steel weight, simplification of the plant design/layout, other important fast reactor design issues, and how to solve feese problems. 

In the field of fast reactor design and operational data, the last reference document published by the IAEA was the 1996 Fast Reactor Database (IAEA-TECDOC-866). Since its publication, quite a lot has happened the construction of two new reactors has been laimched, and conceptual/design studies were initiated for various fast reactors, e.g. the Japanese JSFR-1500 and the Russian BN-1800 (both cooled by sodium), as well as for a wholly new line of LMFR concepts — modular reactors cooled by sodium and by lead-bismuth alloy, and prototype and demonstration conunercial size fast reactors cooled by lead. 

A second consideration, which is peculiar to the fast reactors, exists. Some licensing authorities may simply forbid fast reactor designs to exhibit a positive coolant void worth, even when the overall power coefficient of reactivity is negative. For deployments of fast reactors in countries where that would be the case, two options are available ... 

Lead Fast Reactor Design and Safety, Nuclear Engineering Division, Argonne National Laboratory (ANL),... 

The AHTR facility layout (Fig. 2) is similar to that for the S-PRISM sodiiun-cooled fast reactor designed by General Electric. Both reactors operate at low pressure and high temperature thus, they have similar design constraints. The 9.2-m diameter vessel of the AHTR is the same size as that used by the S-PRISM. Earlier engineering studies indicated that this was die largest practical size of low-pressure reactor vessel. The vessel size determines the power output. For our initial studies, we assumed fuel and power densities (8.3 W/cm ) to be similar to those of MHTGRs. 

Structural materials are used as fuel cladding and assembly wrappers, and also as fuel stabilisers. In connection with fast reactors designed as plutonium burners there is an interest in fuels which are a dispersion of plutonium oxide particles in a ceramic, such as MgO or MgAh04 (a CERCER fuel) or in a metallic matrix such as Cr, or Cr-W alloy (a CERMET... 

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