2019-3(32)

Nuclear, radiation and environmental safety

Article Name10.26583/GNS-2019-03-01
The Method of Assessment of Radioactive Nitrogen 16N Leaks in Steam Generators Used at Nuclear Reactors of KLT-40 Type
AuthorsA.P. Elokhin*1, S.N. Fedorchenko*2
Address

*National Research Nuclear University Moscow Engineering Physics Institute (NRNU MEPhI), Kashirskoye shosse, 31, Moscow, Russia 115409

**The joint - stock company «Specialized Scientific and Research Institute of Instrumentation»

(JSC «SNIIP»), Raspletin St., 5, Moscow, Russia 123060

1ORCID iD: 0000-0002-7682-8504
 WoS Researcher ID: G-9573-2017

e-mail: elokhin@yandex.ru

2ORCID iD: 0000-0001-6144-915X

WoS Researcher ID: F-3804-2018

e-mail: info@sniip.ru

AbstractThe paper considers the leakage of the radionuclide of nitrogen 16N7 (Т½=7,11 с, E,max= 6,134 MэВ, ν,max = 69%) arising in the 1st loop of the KLT-40 reactor used on icebreakers and floating units (PEB), through the steam generator to the second circuit into which water flows under pressure Pв, with temperature Тв, heats up with the formation of radioactive steam, the output of which is carried out through the spiral steam line of steam generator under high pressure Pп. The content of the specified radionuclide in a pair can be detected and assessed by applying the methods of -radiation spectrometry, measuring the volumetric -activity of steam, measuring the dose rate of -radiation of steam and using a computational model using a simple mathematical apparatus to determine the leakage region. The work identifies the main areas in the design of the steam generator, which can be used to measure radiation characteristics and methods for their assessment.
Keywordspower reactor, radionuclide, steam generator, pressure temperature, dose rate, radiation safety.
LanguageRussian
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