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AbstractAbstract
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Transactions of the American Nuclear Society 1975 annual meeting; New Orleans, LA; 8 Jun 1975; Published in summary form only.
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Transactions of the American Nuclear Society; v. 21 p. 260-261
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AbstractAbstract
No abstract available
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ANS annual meeting; San Diego, CA, USA; 18 Jun 1978; See CONF-780622--. Published in summary form only.
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Transactions of the American Nuclear Society; v. 28 p. 157
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AbstractAbstract
No abstract available
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ANS winter meeting; San Francisco, CA, USA; 27 Nov 1977; See CONF-771109--. Published in summary form only.
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Transactions of the American Nuclear Society; v. 27 p. 958-959
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AbstractAbstract
No abstract available
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Source
ANS annual meeting; San Diego, CA, USA; 18 Jun 1978; See CONF-780622--. Published in summary form only.
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Journal Article
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Transactions of the American Nuclear Society; v. 28 p. 336-337
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AbstractAbstract
No abstract available
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Source
ANS annual meeting; San Diego, CA, USA; 18 Jun 1978; See CONF-780622--. Published in summary form only.
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Journal Article
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Conference
Journal
Transactions of the American Nuclear Society; v. 28 p. 385-386
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AbstractAbstract
No abstract available
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Transactions of the American Nuclear Society 1976 international meeting; Washington, DC, USA; 14 Nov 1976; Published in summary form only.
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Transactions of the American Nuclear Society; v. 24 p. 509-510
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AbstractAbstract
No abstract available
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Source
Transactions of the American Nuclear Society 1976 international meeting; Washington, DC, USA; 14 Nov 1976; Published in summary form only.
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Journal Article
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Transactions of the American Nuclear Society; v. 24 p. 510
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AbstractAbstract
[en] Due to the superior nuclear properties of 233U, thorium-based reactors are receiving increasing attention. Because of the relatively high neutron yield of 233U in the thermal range, the thorium-233U fuel system has a higher conversion ratio in thermal reactors than 238U-based fuel systems. Moreover, the thorium-233U system is advantageous in that it produces significantly fewer toxic nuclides of plutonium, americium, and neptunium isotopes. Thorium-based cycles do have some problems, such as slow 233U buildup and the need of additional neutron source initially. In addition, the existence of hard gamma emitters makes it very difficult to reprocess discharged fuel, which is at the same time a positive factor for nonproliferation. Recently, Radkowsky proposed a new type of thorium-fueled reactor, consisting of seed-blanket fuel assemblies, that could be compatible with the existing light water reactor (LWR) technology and could overcome the problems of the thorium fuel cycle. In this paper, the results of a preliminary study on this seed-blanket thorium-based fuel assembly are reported and compared with a standard LWR assembly (ABB/CE type)
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Source
1997 American Nuclear Society (ANS) winter meeting; Albuquerque, NM (United States); 16-20 Nov 1997; CONF-971125--
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Hoffman, E.A.; Hill, R.N.; Taiwo, T.A.
Argonne National Lab., Argonne, IL (United States)
Argonne National Lab., Argonne, IL (United States)
AbstractAbstract
[en] Numerous studies have shown the effectiveness of inert matrix fuel (IMF) in destroying fissile plutonium; however, further recycle is difficult because of the degradation of the fuel vector and the potentially positive void reactivity coefficient (VRC). Selected results from the current study are summarized
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ANS 2005 Winter Meeting; Washington, DC (United States); 13-17 Nov 2005; ANL/NE/CP--116549; AC02-06CH11357; Also available from Argonne National Lab., Argonne, IL (US)
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Transactions of the American Nuclear Society; ISSN 0003-018X; 
; v. 93; p. 363-364
; v. 93; p. 363-364
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AbstractAbstract
No abstract available
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Source
1978 winter meeting of American Nuclear Society; Washington, DC, USA; 12 - 16 Nov 1978; CONF-7811109--; Published in summary form only.
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Transactions of the American Nuclear Society; v. 30 p. 59-61
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