Calculation and instrumentation method of assessment of radioactive nitrogen 16N7 leaks in steam generators applied at KLT-40 type nuclear reactors

Author:

Elokhin Alexandr,Fedorchenko Stanyslav

Publisher

AIP Publishing

Reference17 articles.

1. Dismantling of MR-Reactor IN-Vessel Setups

2. E. A. Ivanov, I. V. Pyrkov and L. P. Khamyanov, Methodology of Diagnosis of Primary Coolant Leak Into the Tank Water of Steam Generators at NPPs with VVER-440 and VVER-1000 Type Reactors, Atomic Energy 77(1), 51–58 (1994).

3. “Methodology (Algorithm) of Calculation of a Leak of Primary Coolant Into Water of Steam Generators at the Kalinin NPP under Continuous Oversight”, Ministry for Atomic Energy of the Russian Federation. Federal State Unitary Subsidiary Enterprise All-Russian Research Institute for Nuclear Power Plants (FSUS VNIIAES), RD EO 0334-02 (30 June 2002).

4. Radiation Safety Rules NRB-99/2009, Sanitary Rules and Standards SanPiN 2.6.1.2523-09.

5. V. I. Deyev, N. V. Schukin and A. L. Tcherezov, Fundamentals of Calculations for Ship Nuclear Power Installations, Training Material/Under General Editorship by prof. I. Deyev (NRNU MEPhI, Moscow, 2012), p. 256 (see also Reactor plant KLT-40 evidence from the nuclear power installation at lighter aboard ship “SevMorPut” http://www.nucon.us/archives/2950).

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