Waste supernate stored in Tank 11H was analyzed periodically from May 1973-August 1975 to determine the rate of nitrite ingrowth by radiolytic decomposition of nitrate. This waste was transferred to tank 33F in accordance with TA 2-892, Rev. 1, 'Use of Cracked Tank for Fresh High Level Waste,' during the week of November 10, 1975. This letter summarizes analytical and corrosion characterization which indicate that this transfer should not increase the risk of stress corrosion cracking in F Area non-stress-relieved tanks. An interpretation of the nitrite ingrowth data is presented and used as a basis for cokncluding that the crack in Tank 11H occurred early in 1974. The formation of nitrite in waste supernate was followed for 2 1/4 years during the last filling and storage cycle in 11H. The conversion of nitrate to nitrite in the 1 1/2 year period after filling was 4.9 x 10{sup -11} mol NO{sub 2}{sup -}/{ell} BTU of fission product heat. The energy released during the period was 1.15 x 10{sup 10} BTU with a corresponding increase in nitrite of 0.56 mol/{ell}. The crack that was first observed in Tank 11H in April 1974 probably made its final penetration through the wall in March …

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A simple analytic method is developed, based on physical approximations, for treating transient implosive longitudinal compression of bunches of heavy ions in an accelerator system for ignition of inertial-confinement fusion pellet targets. Parametric dependences of attainable compressions and of beam path lengths and times during compression are indicated for ramped pulsed-gap lines, rf systems in storage and accumulator rings, and composite systems, including sections of free drift. It appears that for high-confidence pellets in a plant producing 1000 MW of electric power the needed pulse lengths cannot be obtained with rings alone unless an unreasonably large number of them are used, independent of choice of rf harmonic number. In contrast, pulsed-gap lines alone can meet this need. The effects of an initial inward compressive drift and of longitudinal emittance are included.

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Fluidized bed incineration and waste fixation processes are being used to process the types of wastes expected from nuclear fuel reprocessing and production plants. Test incineration runs have been made on two types of wastes: high efficiency particulate air (HEPA) filters and tributyl phosphate-solvent solutions. Laboratory-scale vitrification equipment was used to produce glass pellets from incinerator ash and blends of other expected waste streams. Computer modeling gave an expected product integrity life of over 2,000 years.