Atomic Energy Organization of Iran. Final Safety Analysis Report (FSAR) for BNPP: Accident Analysis [Report]. Unknown Publisher; 2007. [
Link]
nrc.gov [Internet]. Washington: United States Nuclear Regulatory Commission; 2016 [Unknown cited] Available from: Not Found [
Link]
Svenson O. A decision theoretic approach to an accident sequence: When feedwater and auxiliary feedwater fail in a nuclear power plant. Reliability Engineering & System Safety. 1998;59(2):243-252. [
Link] [
DOI:10.1016/S0951-8320(97)00127-0]
Gencheva R, Stefanova A, Groudev P. Investigation of steam line break accident during the development of emergency operating procedures for VVER440/V230. Institute for Nuclear Research and Nuclear Energy, Tzarigradsko Shaussee: 2002. [
Link]
Muellner N, Giannotti W, D'Auria F. Investigation of a possible emergency procedure for the VVER1000 NPP in case of total loss of feed water and a main steam line break. Proceedings of the 12th International Conference on Nuclear Engineering; Arlington, Virginia: 2004, April 25-29. New York; American Society of Mechanical Engineers; 2004. [
Link] [
DOI:10.1115/ICONE12-49036]
Pavlova MP, Groudev PP, Stefanova AE, Gencheva RV. RELAP5/MOD3.2 sensitivity calculations of loss-of-feed water (LOFW) transient at unit 6 of Kozloduy NPP. Nuclear engineering and design. 2006;236(3):322-331. [
Link] [
DOI:10.1016/j.nucengdes.2005.08.009]
Bucalossi A, Del Nevo A, Moretti F, D'Auria F, Elkin IV, Melikhov OI. Investigation of accident management procedures related to loss of feed water and station blackout in PSB-VVER integral test facility. Nuclear Engineering and Design. 2012;250:633-645. [
Link] [
DOI:10.1016/j.nucengdes.2012.06.027]
Lim J, Choi SW, Yang J, Lee DY, Rassame S, Hibiki T, Ishii M. Assessment of passive safety system performance under main steam line break accident. Annals of Nuclear Energy. 2014;64:287-294. [
Link] [
DOI:10.1016/j.anucene.2013.05.032]
Pavlova M, Andreeva M, Groudev P. Steam line break investigation at full power reactor for VVER-1000/V320. Nuclear Engineering and Design. 2015;285:65-74. [
Link] [
DOI:10.1016/j.nucengdes.2015.01.006]
Atomic Energy Organization of Iran. Final safety analysis report (FSAR) for BNPP: Introduction and general description of NPP [Report]. Unknown Publisher; 2007. [
Link]
US Nuclear Regulatory Commission. RELAP5/MOD3.2 Code Manual: Code structure, system models, and solution methods. Idaho: National Engineering Laboratory; 2001. [
Link]
Mozaffari M. Simulation of the effect of a small break loss of coolant accident (SBLOCA) transient on VVER-1000 reactor pressure vessel parameters [Dissertation]. Shiraz: University of Shiraz; 2006. [
Link]
US Nuclear Regulatory Commission. RELAP5/MOD3.2 Code Manual: Code structure, system models, and solution methods. Idaho: National Engineering Laboratory; 2001. [
Link]
Allis-Chalmers Manufacturing Company. Steam System and feed water system failures [Internet]. Washington: United States Nuclear Regulatory Commission; 1962 [Unknown cited]. Available from: https://digital.library.unt.edu/ark:/67531/metadc872288/m1/1/ [
Link]
Luitjens J. Code calibration and validation framework. Idaho: Idaho National Laboratory; 2011. [
Link]
Kliment T, Kvizda B, Zold T. Small break LOCA analysis of Mochovce NPP VVER-440/213 with operator action. Proceeding of the 6th International Information Exchange Forum on Safety Analysis Nuclear Power Plants VVER RBMK Types (Forum-6), 2002, April 8-12, Kiev, Ukraine; 2002. [
Link]
