SCOPUS 정보 검색 플랫폼 - 논문 보기

메뉴 건너뛰기

Nuclear Technology

Volumn 136, Issue 3, 2001, Pages 342-353

Separation of actinides from LWR spent fuel using molten-salt-based electrochemical processes

(5) Karell, E J a Gourishankar, K V a Smith, J L a Chow, L S a Redey, L a

a ARGONNE NATIONAL LABORATORY (United States)

Author keywords

Actinide recovery; LWR fuel cycle; Pyroprocessing

Indexed keywords

ELECTROCHEMISTRY; FAST REACTORS; LITHIUM; SPENT FUELS; URANIUM;

ACTINIDE RECOVERY; INTEGRAL FAST REACTOR; OXIDE SPENT LIGHT WATERREACTOR; PYROPROCESSING;

ACTINIDES;

EID: 0035584118 PISSN: 00295450 EISSN: None Source Type: Journal
DOI: 10.13182/NT136-342 Document Type: Article

Times cited : (51)

References (9)

1
- 0000705671
- Development of pyroprocessing technology
- (1997) Prog. Nucl. Energy , vol.31 , pp. 131
- Laidler, J.J.¹ Battles, J.E.² Miller, W.E.³ Ackerman, J.P.⁴ Carls, E.L.⁵

2
- 0006887642
- Electrometallurgical treatment of TMI-2 fuel debris
- (1997) Trans. Am. Nucl. Soc. , vol.76 , pp. 73
- Karell, E.J.¹ Gourishankar, K.V.² Johnson, G.K.³

3
- 0006981386
- American Nuclear Society
- (2000) Proc. Topl. Mtg. DOE Spent Nuclear Fuel and Fissile Material Management, San Diego, California, June 4-8, 2000 , pp. 65
- Gourishankar, K.V.¹ Karell, E.J.² Everhart, R.E.³ Indacochea, E.⁴

4
- 6644221643
- Chemical partitioning technologies for an ATW system
- (2001) Progr. Nucl. Energy , vol.38
- Laidler, J.¹ Burris, L.² Collins, E.³ Duguid, J.⁴ Henry, R.⁵ Hill, J.⁶ Karell, E.⁷ McDeavitt, S.⁸ Thompson, M.⁹ Williamson, M.¹⁰ Willit, J.¹¹

5
- 0033321338
- Application of lithium in molten-salt reduction processes
- C. EDWARD ECKERT, Ed., The Minerals, Metals, and Materials Society, Warrendale, Pennsylvania
- (1999) Light Metals , pp. 1123
- Gourishankar, K.V.¹ Karell, E.J.²

6
- 0031336637
- 3 (Ln=Nd,Ce)
- (1997) Metall. Mater. Trans. B , vol.28 B , pp. 1103
- Gourishankar, K.V.¹ Johnson, G.K.² Johnson, I.³

7
- 0006932678
- Pyroprocessing oxide spent nuclear fuels for efficient disposal
- American Nuclear Society
- (1994) Proc. Topl. Mtg. DOE Spent Nuclear Fuel-Challenges and Initiatives, Salt Lake City, Utah, December 13-16, 1994 , pp. 275
- McPheeters, C.C.¹ Pierce, R.D.² Mulcahey, T.P.³

8
- 0006885269
- Treatment of oxide spent fuel using the lithium reduction process
- American Nuclear Society
- (1996) Proc. Topl. Mtg. DOE Spent Nuclear Fuel & Fissile Material Management, Reno, Nevada, June 16-20, 1996 , pp. 352
- Karell, E.J.¹ Pierce, R.D.² Mulcahey, T.P.³

9
- 0006921877
- Electrorefining 'N' reactor fuel
- American Nuclear Society
- (1994) Proc. Topl. Mtg. DOE Spent Nuclear Fuel-Challenges and Initiatives, Salt Lake City, Utah, December 13-16, 1994 , pp. 267
- Gay, E.C.¹ Miller, W.E.²

* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.