Status of the Waste Solidification Demonstration Program

McElroy, J.L.; Blasewitz, A.G.; Schneider, K.J.

doi:10.13182/nt71-a15900

Cited by 3 publications

(3 citation statements)

References 8 publications

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“…2,3 Mercury may require a special off-gas system, and sulfate and fluoride may cause excessive corrosion of the process equipment. In the case of boro-silicate glasses, sulfates separate from the melt as a phase that floats; such a phase is highly leachable after the glass has cooled.…”

Section: Glasses and Ceramicsmentioning

confidence: 99%

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Solid forms for Savannah River Plant high-level waste

Wallace¹,

Hull²,

Bradley³

1973

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Section: Glasses and Ceramicsmentioning

confidence: 99%

“…McElroy et al 3 ' showed that 25% of the cesium in a calcine made by the pot calcination process was leached within a week. Of the calcines, the low-temperature solidification product (NaN0 3 ) is probably the best (assuming radiation stability is adequate) because it can be cast into monoliths.…”

Section: Combined Wastesmentioning

confidence: 99%

Solid forms for Savannah River Plant high-level waste

Wallace¹,

Hull²,

Bradley³

1973

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“…(4) Between November 1966 and October 1970, the pot calcination, spray solidification, and phosphate glass solidification processes, developed by Oak Ridge National Laboratory, BattelleNorthwest and Brookhaven National Laboratory, respectively, were demonstrated at the Pacific Northwest Laboratory for the Atomic Energy Commission on an engineering scale with full radioactivity levels. ( 5 An important purpose of these waste solidification demonstrations was to assist in providing the technological bases for the establishment of a high level radioactive waste management policy in the United States. A policy was officially announced in the Federal Register, November 14, 1970.…”

Section: N T H E S O L I D S S T O R a G E Engineeri N G T E S T F mentioning

confidence: 99%

Waste Solidification Program. Volume 10. Evaluation of Solidified Waste Products.

Mendel¹,

McElroy²

1972

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t a l l i n e ceramic, ( 3 ) phosphate g l a s s , and ( 4 ) b o r o s i l i c a t e g l a s s . A t o t a l of 4,930 kg of s o l i d i f i e d w a s t e , c o n t a i n i n g 51,800,000 c u r i e s i n i t i a l l y , was e n c a p s u l a t e d i n 33 c o n t a i n e r s ( p o t s ) . The mild s t e e l , 304L and 310 s t a i n l e s s s t e e l p o t s c o n t a i n i n g t h e s o l i d i f i e d w a s t e s , each8 f e e t l o n g , r a n g e from 6 t o 1 2 i n c h e s i n d i a m e t e r , and a r e v e r y r e p r e s e n t a t i v e of t h e s o l i d i f i e d w a s t e p o t s which w i l l be produced by power r e a c t o r f u e l r e p r o c e s s o r s f o r many y e a r s t o come. Nominal f i s s i o n p r o d u c t o x i d e c o n t e n t of t h e s o l i d s r a n g e s from 9 t o h i g h s of 47 and 82 weight p e r c e n t i n g l a s s and c a l c i n e p r o d u c t s , r e s p e c t i v e l y . The p o t s c o n t a i n i n g t h e s o l i d i f i e d w a s t e s have now beeni n i n t e r i m s t o r a g e from 2 t o 6 y e a r s . C u r r e n t l y 23 a r e i n a i r a t ambient t e m p e r a t u r e , and 1 0 i n t h e S o l i d s S t o r a g e Engineeri n g T e s t F a c i l i t y (SSETF) i n a i r o r water a t c o n t r o l l e d tempera-

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Hazards and control of ruthenium in the nuclear fuel cycle

Eichholz

1978

Progress in Nuclear Energy

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Status of the Waste Solidification Demonstration Program

Cited by 3 publications

References 8 publications

Solid forms for Savannah River Plant high-level waste

Solid forms for Savannah River Plant high-level waste

Waste Solidification Program. Volume 10. Evaluation of Solidified Waste Products.

Hazards and control of ruthenium in the nuclear fuel cycle

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