Vol. 3

Detalhes bibliográficos
Parent link:Scientific, Technical and Engineering Work to Ensure the Safety of the Former Semipalatinsk Test Site: in 3 volumes/ N. A. Nazarbayev [и др.]. Vol. 3.— , 2017.— 978-90-827148-0-7
Resumo:The third volume presents the main results of the research, performed from 1991 to the present day at the NNC's experimental research facilities within the former STS: the Baikal-1 and IGR research reactor complexes. Problem issues were addressed, pertaining to the collection and storage of radioactive waste and sources of ionising radiation, the storage of spent nuclear fuel from the BN-350 and IGR reactors, the repatriation to Russia of highly-enriched nuclear fuel from the IVG.l and RA reactors and the possible conversion of the IVG.1M and IGR reactors to low-enriched fuel. Experimental research was also performed, into the security of nuclear engineering sites and reactor material science.
Publicado em: 2017
Assuntos:
Formato: Livro
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=338604

MARC

LEADER 00000nam2a2200000 4500
001 338604
005 20231102005050.0
010 |a 9789082714838 
035 |a (RuTPU)RU\TPU\book\365106 
035 |a RU\TPU\book\365105 
090 |a 338604 
100 |a 20171128d2017 k y0engy50 ba 
101 0 |a eng 
102 |a GB 
105 |a a z 011zy 
200 0 |a Vol. 3 
210 |d 2017 
215 |a 575 p.  |c il. 
320 |a References: p. 561-575 
330 |a The third volume presents the main results of the research, performed from 1991 to the present day at the NNC's experimental research facilities within the former STS: the Baikal-1 and IGR research reactor complexes. Problem issues were addressed, pertaining to the collection and storage of radioactive waste and sources of ionising radiation, the storage of spent nuclear fuel from the BN-350 and IGR reactors, the repatriation to Russia of highly-enriched nuclear fuel from the IVG.l and RA reactors and the possible conversion of the IVG.1M and IGR reactors to low-enriched fuel. Experimental research was also performed, into the security of nuclear engineering sites and reactor material science. 
461 1 |0 (RuTPU)RU\TPU\book\327216  |y 978-90-827148-0-7  |t Scientific, Technical and Engineering Work to Ensure the Safety of the Former Semipalatinsk Test Site  |o in 3 volumes  |f N. A. Nazarbayev [и др.]  |v Vol. 3  |d 2017 
606 1 |a Ядерные реакторы  |x Испытание  |2 stltpush  |3 (RuTPU)RU\TPU\subj\21633  |9 46590 
610 1 |a захоронение 
610 1 |a ядерные испытания 
610 1 |a научно-технические разработки 
610 1 |a инженерные расчеты 
610 1 |a безопасность 
610 1 |a реакторные конструкции 
610 1 |a исследования 
610 1 |a результаты 
610 1 |a переработка 
610 1 |a радиактивные отходы 
610 1 |a хранение 
610 1 |a хранилища 
610 1 |a инфраструктура 
610 1 |a исследовательские реакторы 
610 1 |a низкообогащенное топливо 
610 1 |a развитие 
610 1 |a ядерная энергия 
610 1 |a преобразование 
610 1 |a ядерная техника 
610 1 |a модернизация 
610 1 |a АЭС 
610 1 |a аварии 
610 1 |a последствия 
610 1 |a термоядерные реакторы 
610 1 |a монографии 
610 1 |a английский язык 
675 |a 621.039.5  |v 4 
801 1 |a RU  |b 63413507  |c 20171128 
801 2 |a RU  |b 63413507  |c 20171212  |g RCR 
942 |c BK