referat.am kursayinner referatner diplomayinner tezer պատվիրել աշխատանքներ description_1
[1] Klein-Heßling W., et al. COCOSYS V2.3 User’s Manual, Revision 0, Draft version from January 16, 2007, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH
[2] RELAP5/MOD3.2 code manual volume I
[3] RADTRAD: A Simplified Model for RADionuclide Transport and Removal And Dose Estimation. NUREG/CR-6604
[4] Accident analysis LOCA 150mm diameter break accident, ARMATOM, ANPP SAR
[5] Confinement thermal-hydraulic analyses, RT-ARMATOM-01/11_-01_111115_rev01
[6] Analysis of Radiological Consequences of DBA and BDBA and Specification of Emergency Arrangement Zones, April 30, 2011, VUJE
[7] Правила Ядерной Безопасности Реакторных Установок Атомных Станций (ПБЯ РУ АС - 89) ПНАЭ Г-1-024-90, 1990
[7a] Russian science centre “Kurchatov Institute”, Instruction for controlling fuel cladding tightness for VVER-440 (type V-230 and V-213) during operation and shutdown regimes, Moscow, 1998
[8] Russian science centre “Kurchatov Institute”, Calculation of gap inventory for ANPP Unit 2, Moscow, 2009
[9] Fauske & Associates, Inc., FAI Aerosol Correlation, An Industry Degraded Core
Rulemaking (IDCOR) Program Report, Bethesda, MD, 1984.
[10] D. A. Powers and S. B. Burson, “A Simplified Model of Aerosol Removal by
Containment Sprays,” NUREG/CR-5966, SAND92-2689, Sandia National Laboratories,Albuquerque, NM, 1993.
[11] US NRC, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,” NUREG-0800.
[12] R.K.Hilliard, L.F.Coleman, C.E.Linderoth, J.D.McCormack, A.K.Postma,
“Removal of Iodine and Particles from Containment Atmospheres by Sprays” Containment Systems Experiment Interim Report, BNWL-1244, Battelle Memorial Institute Pacific Northwest Laboratories, Richland, Washington 99352
[13] Advice on Source term, e-mail from June 26, 2011, by Josef Misak
[14] European Utility Requirements for LWR Nuclear Power Plants, April 2001
[15] Additional data for RC calculation, e-mail from 3/3/2011, by Juraj Klepac
[16] U.S. Nuclear and Regulation Commission,
Alternative radiological source terms for evaluating design basis accidents at nuclear power reactors, regulatory guide 1.183, July 2000
[17] S.Bznuni. Core Inventory Database Development for Radiological Consequences Analysis. NRSC-ARMATOM-01-09, Yerevan, 2009
List of Acronyms
ANPP -Armenian Nuclear Power Plant
DBA - Design Base Accident
BDBA - Beyond Design Base Accident
ECCS - Emergency Core Cooling System
LOCA - Loss of Coolant Accident
NPP - Nuclear Power Plant
NBS -Spray system pump
PRZ - Pressurizer
IAEA - International Atomic Energy Agency
SG - Steam Generator
TEDE - Total effective dose equivalent
CEDE - Committed effective dose equivalent
TH -Thermo-hydraulics
RM -Radioactive materials
Figure 5 Integral leakages from confinement
Figure 7 Integral release from confinement flaps
Figure 9 Integral iodine activity in environment
Figure 11 Integral noble gases activity in envi
Figure 13 Integral cesium activity in environment
Figure 15 Activity of I-131 in Environment
Figure 17 Activity of I-131 in Confineme
Figure 19 Activity of I-131 in Volume 1
Figure 21 Activity of I-131 in Volume 2
Figure 23 Activity of I-131 in Volume 3
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