FFTF

The United States continued fast-breeder reactor research and development with the building of the fast flux test faciHty (FFTF) at Hanford and the SEFOR reactor in Arkansas (59). The next plaimed step was to build a prototype power reactor, the Clinch River fast-breeder plant (CRFBP), which was to be located near Oak Ridge, Teimessee. 

It is illustrated in Section 3.4.4 by tracing the paths for leaking engine compression and applied to fault tree construction for the FFTF reactor Fullwood and Erdmann, 1974). The method involves writing Boolean equations for all paths whereby hazardous material may be released. It is primarily useful for enumerating release paths, but not for what started the release It was used to enumerate the possible paths for stealing nuclear bomb material from a facility. 

Fast flux test facility (FFTF), 17 587 Fast Fourier transform (fft) algorithm, 23 137. See also Fourier entries Fast gas chromatography, 6 434-437 Fastin, 3 91, 93t... 

ASTM standard /z-Butyl D 304-85 Isobutyl D 1719-86. fftf-Butyl D 1007-85 Specification method... 

At present, americium is separated and purified in Kg/yr quantities at the new plutonium facility at Los Alamos (Figure 1). The feed for the americium production comes from a line which produces high purity ceramic grade Pu02 for the Fast Flux Test Facility (FFTF) at Richland, Washington. The feed for this FFTF PuO is aged plutonium metal which contains sizable amounts of 24 Am... 

The flowsheet for the FFTF Pu02 production is shown in Figure 2. Briefly, the plutonium metal is converted to an impure oxide by burning the metal in air. This is followed by dissolution of the impure oxide in a 15.6 M HN03 - 0.5 M HF solution. The americium is separated from the plutonium by precipitation of the plutonium as the peroxide. Americium does not form an insoluble peroxide and stays in the filtrate with other cationic impurities. The active peroxide filtrate is slowly dripped into 9 M NaOH. The combination of strong alkali and heat destroys the peroxides and precipitates the americium as the hydroxide. Any residual plutonium in the filtrate, along with other cations, is precipitated also as the hydroxide. The flowsheet for the americium oxide production is shown in Figure 3. 

Fast breeder reactor fuel rods consist of stainless-steel-clad mixed oxide (U,Pu)02 fuel however, more stable alloys for cladding and in-core structural materials, with resistance to swelling and embrittlement under fast neutron irradiation, and more efficient fuels (carbide see 17.3.12.1.2) or nitride (see 17.3.12.3)] are needed h The mechanical, metallurgical, and chemical processes in fuel element irradiation are depicted in Figure 1. Figure 2 shows the PFR (U.K.) fast breeder fuel element, and Figures 3 and 4 illustrate the Fast Flux Test Facility (FFTF) fuel system. 

Figure 6. FFTF fuel fabrication demonstration facility. (After Ref. 8.)...

LMFRs(liquid metal cooled reactor) have been under development for more than 50 years. Twenty LMFRs have been constructed and operated. Five prototype and demonstration LMFRs (BN-350/Kazakstan, Phenix/France, Protot3q)e Fast Reactor/UK, BN-600/Russian Federation, Super Phenix/France) with electrical output ranging from 250 to 1200 MW(e) and large scale (400 MW(th)) experimental fast flux test reactor FFTF/USA have gained nearly 110 reactor-years. In total, LMFRs have gained nearly 310 reactor-years of operation. 

G.J. CALAMAI et al. Steady State Thermal and Hydraulic Characteristics of the FFTF Fuel Assemblies, FRT-1582, 1974. (Cit. by A.E. WALTAR, A.B. REYNOLDS, Fast Breeder Reactors, Perg. Press., N.Y., 1981)... 

Exchange detailed technical information on fast reactor operation and/or decommissioning experience with DFR, PFR (UK) KNK-II (Germany) Rapsodie, Phenix, Superphenix (France) BR-10, BOR-60, BN-600 (Russian Federation) BN-350 (Kazakhstan) SEFOR, EBR-II, Fermi, FFTF (USA) FTBR (India) JOYO, MONJU (Japan) ... 

Horn J.E., Michaels T.E., Sheen E.M., and Yatabe J.M. viewing development for FFTF." pp4-37 to 4-43, Second conference on liquid metal technology, C0NF-800401-P1,... 

Sodium release to RGB under CD A has been estimated at about 1.5 t, based on the approach followed for FFTF reactor. The important input to this analysis are the transient and quasi-static pressure of the sodium after slug impact beneath the top shield and the fraction of the sodium mass in the reactor assembly which has potential to get ejected. These parameters are obtained from the detailed fast transient fluid-structure interaction analysis using an in-house computer code called FUSTIN. A preliminary estimate is also made on the transient pressure and temperature rise in the RGB for the 1.5 t of sodium release and the values are 30 kPa and 80 K respectively. 

The PIE of fuel subassemblies of PNC316 steel and PNC 1520 advanced austenitic stainless steel inadiated in FFTF has been successfully completed. The 2nd shipment of irradiated fuel materials to OEC was conducted to take a further investigation of high bumup fuel behavior. 

Excluding military and space reactors, approximately 20 sodium-cooled fast reactors have been built in a variety of sizes and configurations. These vary from small test reactors to the French Super-Phenix plant, which had an output of 1240 MW(e). In the United States, several fast reactors were built. These included the EBR-II and the Fast-Flux Test Facility (FFTF)—a 400-MW(t) reactor. The Clinch River Breeder Reactor Plant (CRBRP), a commercial demonstration reactor, was designed and partly built before being cancelled. These machines provide a large experience base in refueling operations (Romrell et al., 1989 Althaus and Brahy, 1987). 

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