Results 61 to 70 of about 2,207 (187)

COMPASS - New modeling and simulation approach to PWR in-vessel accident progression

Nuclear Engineering and Technology, 2019
The objective of this paper is to discuss the modeling principles of phenomena governing core degradation/melting and in-vessel melt relocation during severe accidents in light water reactors.
Michael Z. Podowski, Raf M. Podowski, Dong Ha Kim, Jun Ho Bae, Dong Gun Son   +4 more
doaj   +1 more source

Experimental investigation of sodium boiling heat exchange in fuel subassembly mockup for perspective fast reactor safety substantiation

Nuclear Energy and Technology, 2015
Numerical modeling of ULOF-type accident development in sodium-cooled fast reactor carried out using the COREMELT code indicate the development and spreading of sodium boiling in the core accompanied with fluctuations of reactor technological parameters ...
R.R. Khafizov, V.M. Poplavsky, V.I. Rachkov, A.P. Sorokin, Yu.M. Ashurko, A.V. Volkov, E.F. Ivanov, V.V. Privezentsev   +7 more
doaj   +1 more source

Evaluation of heat-flux distribution at the inner and outer reactor vessel walls under the in-vessel retention through external reactor vessel cooling condition

Nuclear Engineering and Technology, 2015
Background: A numerical simulation was carried out to investigate the difference between internal and external heat-flux distributions at the reactor vessel wall under in-vessel retention through external reactor vessel cooling (IVR-ERVC). Methods: Total
Jaehoon Jung, Sang Mo An, Kwang Soon Ha, Hwan Yeol Kim   +3 more
doaj   +1 more source

Light-water reactor accident classification [PDF]

, 1980
The evolution of existing classifications and definitions of light-water reactor accidents is considered. Licensing practice and licensing trends are examined with respect to terms of art such as Class 8 and Class 9 accidents. Interim definitions, consistent with current licensing practice and the regulations, are proposed for these terms of art.
openaire   +2 more sources

Simulated safety analysis of a total loss of feedwater accident in the steam generator of CPR1000 nuclear power plant

Frontiers in Energy Research
As M310 series units, CPR1000 Nuclear Power Plant in China is also the first batch of demonstration nuclear power plants in China to try out SOP(the state-oriented procedure) accident procedures.
Guanyi Wang, Chaoying Zheng, Yang Zhang, Peng Wu, Fangqiang Chen   +4 more
doaj   +1 more source

CARNSORE: Hypothetical reactor accident study

, 1984
Two types of design-basis accident and a series of hypothetical core-melt accidents to a 600 MWe reactor are described and their consequences assessed. The PLUCON 2 model was used to calculate the consequences which are presented in terms of individual and collective doses, as well as early and late health consequences.
Walmod-Larsen, Niels Ole, Jensen, Niels Otto, Kristensen, Leif, Meide, A., Nedergård, K.L., Nielsen, F., Lundtang Petersen, Erik, Petersen, T., Thykier-Nielsen, Søren   +8 more
openaire   +2 more sources

Probabilistic safety analysis of the large primary circuit leakages accident scenarios in the VVER-reactor

Весці Нацыянальнай акадэміі навук Беларусі: Серыя фізіка-тэхнічных навук
Probabilistic safety analysis of the loss of coolant accidents in the VVER-type reactor plant has been performed taking into account the internal initiating events of the reactor primary circuit large leakages.
E. A. Mikhalycheva, A. G. Trifonov
doaj   +1 more source

Benchmark analysis of SPERT III E-core critical experiments using the STREAM neutronics code

Nuclear Engineering and Technology
This study delivers a high-fidelity neutronic analysis of the SPERT III E-Core, a pressurized-water experimental reactor designed to probe fundamental transient behavior during reactivity-initiated accidents (RIAs).
Anisur Rahman, Saisundar Mohanty, Deokjung Lee   +2 more
doaj   +1 more source

Modeling of the corium jet penetration into the pool of volatile coolant under reactor vessel [PDF]

Ядерна фізика та енергетика, 2010
Developed mathematical model and some results of its application to the element of the passive protection system against severe accidents at NPP with water pool under reactor vessel for corium melt and particles’ cooling are presented.
V. H. Moghaddam, I. V. Kazachkov
doaj  

Multiphysics analysis of a metal hydride moderated megawatt heat pipe reactor with burnable poisons

Frontiers in Energy Research
With the development of nuclear energy, microreactors have received increasing interest among researchers in recent years. In this paper, a megawatt heat pipe reactor with metal hydride moderators and burnable poisons is proposed.
KuaiYuan Feng, Jipu Hu, Yihu Wang, Tenglong Cong, Hanyang Gu, Hui Guo   +5 more
doaj   +1 more source