刊名:Journal of Radioanalytical and Nuclear Chemistry
出版年:2016
出版时间:February 2016
年:2016
卷:307
期:2
页码:1045-1053
全文大小:881 KB
参考文献:1.Lehto Y, Hou X (2011) Chemistry and analysis of radionuclides, chapter 6.5. Wiley, Weinheim 2.Nagy P, Vajda N, Sziklai-László I, Kovács-Széles É, Simonits A (2014) Determination of 135Cs in nuclear power plant wastes by ICP-MS and k 0-NAA. J Radioanal Nucl Chem 300(2):615–627CrossRef 3.Herman OW, Westfall RM (2000) ORIGEN-S SCALE system module to calculate fuel depletion, actinide transmutation, fission product buildup and decay, and associated radiation source terms. Oak Ridge National Laboratory, NUREG/CR-0200, vol 2, section F7, ORNL/NUREG/CSD-2/V2/R6 4.Chao J-H, Tseng C-L (1996) Determination of 135Cs by neutron activation analysis. Nucl Instrum Methods A 372:275–279CrossRef 5.Hayes AC, Jungman G (2012) Determining reactor flux from xenon-136 and cesium-135 in spent fuel. Nucl Instrum Methods Phys 690:68–74CrossRef 6.Neeb K-H (1997) The radiochemistry of nuclear power plants with light water reactors, chapter 4.3. Walter de Gruyter, BerlinCrossRef 7.Lewis BJ, McDonald R, Ivanoff V, Iglesias FC (1993) A review of fuel performance and fission product release studies for defected fuel elements, IAEA-TECDOC-709 8.Vajda N (1995) Fuel performance measurements in nuclear reactors using new analytical procedures, C.Sc. Dissertation
作者单位:Péter Nagy (1) Nóra Vajda (2) Tamás Pintér (3) Kornél Fél (4)
1. Hungarian Trade Licensing Office, 37-39 Németvölgyi, Budapest, 1124, Hungary 2. Radanal Ltd., 29-33 Konkoly-Thege M., Budapest, 1121, Hungary 3. Chemistry Department, Paks Nuclear Power Plant, Paks, Hungary 4. Nuclear Security Department, Centre for Energy Research, Hungarian Academy of Sciences, 29-33 Konkoly-Thege M., Budapest, 1121, Hungary
刊物类别:Chemistry and Materials Science
刊物主题:Chemistry Nuclear Chemistry Physical Chemistry Nuclear Physics, Heavy Ions and Hadrons Diagnostic Radiology Inorganic Chemistry
出版者:Akad茅miai Kiad贸, co-published with Springer Science+Business Media B.V., Formerly Kluwer Academic
ISSN:1588-2780
文摘
Activities of 134Cs, 137Cs and 135Cs were determined in primary coolant samples of VVER-440 reactors. 135Cs was measured by inductively coupled plasma mass spectrometry after radiochemical separation of Cs using AMP–PAN and Dowex-50 cation exchange resin columns. The burnup of the samples was calculated from the 134Cs/137Cs activity ratio while the thermal neutron flux was estimated from the 137Cs/135Cs mass ratio. Conclusions were drawn on the burnup and the thermal neutron flux of defective fuel elements. Keywords 137Cs/135Cs ratio 134Cs/137Cs ratio Neutron flux Burnup Primary coolant