Idaho chemical programs annual technical report, fiscal year 1974

Bower, J.R. ed.

doi:10.2172/4236110

Cited by 2 publications

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“…Recent measurements [41,42,431 of the stability of the fluoride complexes of aluminum, zirconium, and other elements, have made it possible to estimate the fluoride ion concentration or un-ionized HF concentration of complicated solutions and to predict corrosion properties. …”

Section: Direct Correlation Of Corrosion With Uncomplexed Fluoridementioning

confidence: 99%

Corrosion of austenitic stainless steel alloys due to HNO$sub 3$--HF mixtures

Cole¹

1974

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T h i s r e p o r t was p r e p a r e d a s a n a c c o u n t o f w o r k s p o n s o r e d by t h e U n i t e d S t a t e s G o v e r n m e n t . N e i t h e r t h e U n i t e d S t a t e s n o r t h e U n i t e d S t a t e s A t o m i cE n e r g y C o m m i s s i o n , n o r a n y o f t h e i r e m p l o y e e s , n o r a n y o f t h e i r c o n t r a c t o r s , s u b c o n t r a c t o r s , o r t h e i r e m p l o y e e s , makes a n y w a r r a n t y , e x p r e s s or i m p l i e d , o r assumes a n y l e g a 7 I i a b i I i t y o r r e s p o n s i b i I i t y f o r t h e a c c u r a c y , c o m p l e t en e s s o r u s e f u l n e s s o f a n y i n f o r m a t i o n , a p p a r a t u s , p r o d u c t o r p r o z e s s d i sc l o s e d , o r r e p r e s e n t s t h a t i t s u s e w o u l d n o t i n f r i n g e p r i v a t e l y owned r i g h t s . DISCLAIMER €I. S. Cole N O T I C EThis report was prepared as an account of work sponsored by the United States Government. Neither the United States nor the United States Atomic Energy Commission, cor a n j of their empioyees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness or usefulness of any information, apparatus, product or process disclosed, or represents that its use would not infringe privately owned rights. ALLIED CHEMICAL CORPORATION IDAHO CHEMICAL PROGRAMS-OPERATIONS OFFICE ABSTRACTThis report represents a literature survey, plus some experimental work, on the corrosion of austenitic stainless steel alloys due to HN03-HF mixtures. Most of the available data were obtained during the processing of spent nuclear fuel elements where solutions containing nitrates and fluorides are frequently encountered. Austenitic stainless steels have been extensively used in nitrate-fluoride solution service in these plants. It has been shown that their service may be improved by: (1) proper annealing; (2) stabilizing with columbium (niobium) or titanium; ( 3 ) complexing the solutions the stainless steels will contain with aluminum, zirconium, or thorium; (4) utilizing stainless steels which have a low carbon content; ( 5 ) maintaining the uncomplexed hydrofluoric acid in the solution at as low a value as practicable; and (6) utilizing neutron absorbing elements in the alloys at concentrations as low as possible for service as fixed nuclear poisons. Other protective measures such as reduced contact time, temperature, concentration, and fluoride-to-nitrate ratio can be employed to minimize corrosion. n ..

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Section: Direct Correlation Of Corrosion With Uncomplexed Fluoridementioning

confidence: 99%

Corrosion of austenitic stainless steel alloys due to HNO$sub 3$--HF mixtures

Cole¹

1974

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“…To 106,600 gallons of WM-183 first cycle aluminum raffinate waste, between Campaign H-5 and H-6, was added: 6,900 gallons of possible decon solution; 2,900 gallons of possible first cycle Al waste; and 41,000 gallons of first cycle stainless steel nitrate waste (Amberson 1972c;Amberson 1972d;Amberson 1972e;Amberson 1973a;Amberson 1973b;Amberson 1973c;Amberson 1973d). Assuming that the composition of WM-183 waste and stainless-steel nitrate waste prior to the above additions to WM-183 was that given in Bower (1974) Most of the time WM-183 waste was concentrated prior to transferring it to the feed blend tank. Between March 28 and April 19, 1974, when calcining concentrated WM-183 waste, the off-gas final filters had to be changed out frequently, and material removal from the filters turned out to be ammonium magnesium aluminum fluoride hydrate.…”

Section: Wcf Campaign H-5mentioning

confidence: 99%

Summary of Waste Calcination at INTEC

O`Brien¹,

Newby²

2000

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A summary of waste calcination in full-scale and pilot plant calciners has been compiled for future reference. The summary includes feed chemical composition and process operating parameters for: 1) Waste Calcining Facility (WCF) cold operation and hot campaign H-1 through H-9 from 1961 to 1981; 2) New Waste Calcining Facility (NWCF) cold operation and hot campaigns H-1 through H-4 from 1981 to 2000; and 3) smallscale feed blend tests conducted using non-radioactive simulants in various sizes of pilot plant calciners with fluidized-beds from 4 in. diameter up to 2 foot square. These summaries provide a historical record of calcination development at INTEC, give the range of feed compositions and feed additives that have been tested, and will be useful for evaluating calcinability of future wastes.In the calcination process, the liquid wastes are sprayed using air-atomizing nozzles into a fluidized bed of heated spherical calcine particles, evaporating water and nitric acid in the wastes and leaving behind solid-phase metal oxides. Heat was originally provided by re-circulating liquid eutectic sodium/potassium alloy through heat exchange tubes located in the bed. In 1970 the heat input was changed to in-bed combustion (IBC) of kerosene fuel, sprayed directly into the bed through oxygen atomized fuel nozzles, and the calcination temperature was increased to 500 o C. NWCF testing at 600°C with IBC was performed during AprilJune 1999 and April-May 2000.The successful calcination of a given waste is dependent primarily on the major chemical constituents (greater than about 0.05 molar) and the concentration (or diluteness) of dissolved solids in the waste feed. Chemical additives used for calcination have been calcium nitrate to control halide volatility, boric acid to promote amorphous alumina formation, and aluminum nitrate to dilute the sodium content in the calcine. Wastes which were difficult to calcine alone due to diluteness, inability to control particle size, or formation of agglomerates could often be calcined as blends with more amenable wastes. vi vii ACKNOWLEGEMENTS I would like to acknowledge Billie J. Newby for his years of hard work and dedication, over his 30+ years at the Idaho Chemical Processing Plant. His meticulous notes on calcination have been extremely helpful over the years. A great many others, too numerous to mention, worked on calcination development and operation over the years; and they should all be proud to have pioneered the most successful high-level radioactive waste solidification process in the Department of Energy (DOE) complex. I would also like to acknowledge R. M. Gifford for typing and preparing this report for publication.viii ix CONTENTS

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Idaho chemical programs annual technical report, fiscal year 1974

Cited by 2 publications

References 0 publications

Corrosion of austenitic stainless steel alloys due to HNO$sub 3$--HF mixtures

Corrosion of austenitic stainless steel alloys due to HNO$sub 3$--HF mixtures

Summary of Waste Calcination at INTEC

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