Publication: Calculation and instrumentation method of assessment of radioactive nitrogen 16N7leaks in steam generators applied at KLT-40 type nuclear reactors
Дата
2023
Авторы
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Аннотация
The paper studies a primary-to-secondary leak of nitrogen radionuclide 16N7 (РўВЅ=7.11 s, EОі,max= 6.134 MeV, ОЅОі,max = 69%) through a steam generator in a KLT-40 type reactor (used in ice breakers and floating power units, FPUs) with an ingress of water of Pv pressure and Tv temperature heated by a follow-up radioactive steam generation which is released under high pressure Pp through a helical steam duct of the steam generator. Content of the specified radionuclide in steam can be found and estimated by use of methods of gamma-spectrometry, measurement of Оі-activity concentration of steam and Оі-radiation dose rate through the use of a simple physical and mathematical model allowing to specify the reason and to define area of a leakage on a helical steam duct. The paper specifies main areas in the structure of steam generators where radiation characteristics may be measured, and their assessment techniques may be applied. Fig. 8, Table 4, ref. 17.
Описание
Ключевые слова
Pressurized water reactor , Lead-Cooled Fast Reactor , Steam pressure , Leakage (economics)
Цитирование
Elokhin, A. Calculation and instrumentation method of assessment of radioactive nitrogen 16N7leaks in steam generators applied at KLT-40 type nuclear reactors / Elokhin, A., Fedorchenko, S. // AIP Conference Proceedings. - 2023. - 2700. - 10.1063/5.0125107