Investigation of critical safety function “Heat sink” at low power and cold condition for Kozloduy Nuclear Power Plant WWER-1000/V320-Reference-Cited by-同舟云学术

Investigation of critical safety function “Heat sink” at low power and cold condition for Kozloduy Nuclear Power Plant WWER-1000/V320

Published:2012-02 Issue:1 Volume:40 Page:221-228
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Andreeva M.,Pavlova M.P.,Groudev P.P.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference6 articles.

1. Beelman, R.J., 1999. Soviet-designed pressurized water reactor symptomatic emergency operating instruction analytical validation procedure: approach, methodology development and application. SAIC/099-4533/8920-001/00, Rev. 0.

2. Fletcher, C.D., Schultz, R.R., 1995. RELAP5/MOD3 Code Manual, User’s Guidelines. NUREG/CR-5535, INEL-96/0174, vol. 5, Rev.1.

3. Groudev, P.P., Pavlova, M.P., Demerdjiev, P.A., January 1999. Data Base for VVER-1000/V320. SACI of KNPP, BOA 278065-A-R4, INRNE-BAS, Sofia.

4. Groudev, P.P., Pavlova, M.P., Demerdjiev, P.A., April 1999. Engineering Handbook. SACI of KNPP, BOA 278065-A-R4, INRNE-BAS, Sofia.

5. Groudev, P., Pavlova, M., Andreeva, M., 2008. Analytical Validation of Emergency Operating Procedures for VVER-1000/V320 at Low Power of Kozloduy NPP, Report for KzNPP, INRNE-BAS, Sofia.

Cited by 8 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. A review of the assessment of severe accident management guidelines and actions through analytical simulations;Annals of Nuclear Energy;2023-01

2. Thermal-Hydraulics analysis of pressurized water reactor core by using single heated channel model;J APPL COMPUT MECH;2017

3. An assessment of a VVER-1000 core during Turbo-Generator load reduction test using RELAP5/MOD3.2 and WIMSD-5B/PARCSv2.7;Progress in Nuclear Energy;2016-11

4. Analytical validation of operator actions in case of primary to secondary leakage for VVER-1000/V320;Nuclear Engineering and Design;2015-12

5. Steam Line Break investigation at full power reactor for VVER-1000/V320;Nuclear Engineering and Design;2015-04