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Titolo:
Vitrification of borate waste generated by nuclear power plants
Autore:
Sheng, JW; Luo, SG; Tang, BL;
Indirizzi:
Inst Atom Energy, Beijing 102413, Peoples R China Inst Atom Energy Beijing Peoples R China 102413 102413, Peoples R China
Titolo Testata:
NUCLEAR TECHNOLOGY
fascicolo: 1, volume: 125, anno: 1999,
pagine: 85 - 92
SICI:
0029-5450(199901)125:1<85:VOBWGB>2.0.ZU;2-R
Fonte:
ISI
Lingua:
ENG
Soggetto:
GLASS;
Keywords:
vitrification; borate waste; Minimum Additive Waste Stabilization;
Tipo documento:
Article
Natura:
Periodico
Settore Disciplinare:
Engineering, Computing & Technology
Citazioni:
13
Recensione:
Indirizzi per estratti:
Indirizzo: Sheng, JW Korea Elect Power Res Inst, Taejon 305380, South Korea Korea Elect Power Res Inst Taejon South Korea 305380 uth Korea
Citazione:
J.W. Sheng et al., "Vitrification of borate waste generated by nuclear power plants", NUCL TECH, 125(1), 1999, pp. 85-92

Abstract

Berate waste is the main liquid waste generated by nuclear power plants (NPPs). Vitrification is conceptually attractive because of the potential durability of the final product, the flexibility of the process in treating a wide variety of waste streams, and the economy of barge volume reduction. The vitrification of borate waste from NPPs, including the glass formulationand product characterization, is examined. The Minimum Additive Waste Stabilization (MAWS) concept was utilized to design the glass formulation. The glass formulation named SL-1, which can incorporate 45 wt% of waste oxides,was selected. The SL-1 glass has good chemical stability, the melting temperature is 1000 degrees C, and the viscosity of molten glass is similar to 5.0 Pa.s at 1000 degrees C. The borosilicate glass form could satisfactorily solidify berate waste with high volume reduction.

ASDD Area Sistemi Dipartimentali e Documentali, Università di Bologna, Catalogo delle riviste ed altri periodici
Documento generato il 19/09/20 alle ore 21:43:36