METHOD FOR DETERMINING FISSION RADIOIODINE CONTENT IN WATER COOLANT OF NUCLEAR-REACTORS

被引：0
作者：
KULEFF, I [1 ]
TODOROVS.D [1 ]
机构：
[1] UNIV SOFIA,CHEM FAC,SOFIA 26,BULGARIA
来源：
KERNENERGIE | 1972年 / 15卷 / 11-1期
关键词：
D O I：
暂无
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
引用
收藏
页码：381 / 383
页数：3
相关论文
共 50 条
[41]   NUMERICAL METHOD FOR OPTIMIZATION OF HETEROGENEOUS NUCLEAR-REACTORS BY MEANS OF BURNABLE POISON BLOCKS [J].
VORONKOV, AV ;
CHUYANOV, VA .
ATOMNAYA ENERGIYA, 1973, 34 (06) :475-475
[42]   SOME ASPECTS OF MONTE-CARLO METHOD APPLICATION TO NUCLEAR-REACTORS ANALYSIS [J].
GOMIN, EA ;
MAIOROV, LV ;
YUDKEVICH, MS .
PROGRESS IN NUCLEAR ENERGY, 1990, 24 (1-3) :211-222
[43]   THE CECE ALTERNATIVE FOR UPGRADING DETRITIATION IN HEAVY-WATER NUCLEAR-REACTORS AND FOR TRITIUM RECOVERY IN FUSION-REACTORS [J].
SPAGNOLO, DA ;
MILLER, AI .
FUSION TECHNOLOGY, 1995, 28 (03) :748-754
[44]   DESIGN AND DEVELOPMENT OF COMPACT, DURABLE ELECTROMAGNETIC PULSE POWER COILS FOR REPOSITIONING OF COOLANT TUBE SPACERS IN CANDU NUCLEAR-REACTORS [J].
DABLEH, JH ;
FINDLAY, RD ;
KLEMPNER, GS .
IEEE TRANSACTIONS ON ENERGY CONVERSION, 1986, 1 (04) :1-8
[45]   SUMMARY OF THEORETICAL AND EXPERIMENTAL DEVELOPMENT OF A NOVEL ELECTROMAGNETIC TECHNIQUE FOR REMOTE REPOSITIONING OF COOLANT TUBE SPACERS IN CANDU NUCLEAR-REACTORS [J].
FINDLAY, RD ;
DABLEH, JH .
IEEE TRANSACTIONS ON ENERGY CONVERSION, 1988, 3 (02) :285-291
[46]   NUFREQ-NP - A COMPUTER CODE FOR THE STABILITY ANALYSIS OF BOILING WATER NUCLEAR-REACTORS [J].
PENG, SJ ;
PODOWSKI, MZ ;
LAHEY, RT ;
BECKER, M .
NUCLEAR SCIENCE AND ENGINEERING, 1984, 88 (03) :404-411
[47]   A STATE VARIABLE FORMULATION OF DENSITY-WAVE OSCILLATIONS IN BOILING WATER NUCLEAR-REACTORS [J].
SHEN, CN ;
BALARAM, J ;
LAHEY, RT .
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1981, 38 (JUN) :774-776
[48]   EXPERIMENTAL-DETERMINATION OF GAMMA-RADIATION POWER OF FISSION-PRODUCTS IN SHORT OPERATION OF NUCLEAR-REACTORS [J].
MARKINA, MA ;
STARIZNYI, ES ;
BREGER, AK .
SOVIET ATOMIC ENERGY, 1978, 44 (06) :611-613
[49]   DETERMINATION OF THE I-129 CONTENT OF THE PRIMARY COOLANT OF NUCLEAR-POWER REACTORS [J].
KULEFF, I ;
ZOTSCHEV, S ;
STEFANOV, G .
JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY-ARTICLES, 1986, 97 (01) :73-79
[50]   Automatic monitoring of the hydrogen content in the primary coolant of nuclear power stations with VVER reactors [J].
Sinitsyn, V.P. ;
Kruglova, T.K. .
Teploenergetika, 1998, 45 (07)
12345