Results 111 to 120 of about 1,536,451 (138)

Numerical simulation of heat dissipation characteristics in PWR high-pressure coolant pipes during cold shutdown. [PDF]

Sci Rep
Tang F, Wang W, Luo Y, Chen Y, Yan B, Liu S.   +5 more
europepmc   +1 more source

Standard problem for RELAP5 code validation for VVER-440 reactor unit

, 2006
Изложены результаты реализации стандартной проблемы для валидации расчетного кода RELAP5 на базе документальных данных аварии с течью из первого контура во второй на энергоблоке с реактором типа ВВЭР-440.
Борисенко, В.И., Крушинский, А.Г., Мукоид, В.П.   +2 more
core  

Identification and diagnosis of flow instability in parallel channel systems using machine learning. [PDF]

Commun Eng
Peng C, Wang X, Tian R, Wu J, Deng J.
europepmc   +1 more source

Preliminary risk assessment of in-vessel leakage accident in ITER. [PDF]

Sci Rep
Duan Q, Fang X, Chen S, Xie H, Wang C, Wang D.   +5 more
europepmc   +1 more source

An integrated method for the leakage fault mode diagnosis and life prediction of the reactor coolant pump. [PDF]

PLoS One
Shao Y, Kang R, Fu J, Liu J.
europepmc   +1 more source

Analysis of VVER-1000 natural circulation regime for RELAP5 code validation standard problem

, 2011
Изложены основные результаты валидации расчетного кода RELAP5 в рамках международного сотрудничества специалистов Украины и Болгарии при реализации стандартной проблемы для ВВЭР-1000 энергоблока № 6 АЭС «Козлодуй». Приведен сравнительный анализ расчетных
Борисенко, В.И., Грудев П., Крушинский, А.Г., Павлова, М., Мукоид, В.П.   +4 more
core  

Quantification of Uncertainty of Reflood-Related Models of RELAP5 MOD3.3 Code

, 2014
Best-Estimate plus Uncertainty Evaluation methods are gaining increased interest in the licensing process. Besides, lessons learnt from the BEMUSE benchmark and others show that deeper understanding of some present methods is necessary, especially in ...
Kovtonyuk A., D’Auria F., Petruzzi A.
core  

Independent code assessment at BNL in FY 1982. [TRAC-PF1; RELAP5/MOD1; TRAC-BD1]

, 1982
Independent assessment of the advanced codes such as TRAC and RELAP5 has continued at BNL through the Fiscal Year 1982. The simulation tests can be grouped into the following five categories: critical flow, counter-current flow limiting (CCFL) or ...
Neymotin, L., Jo, J.H., Saha, P., Slovik, G., Rohatgi, U.S., Yuelys-Miksis, C.   +5 more
core  

Simulation of condensation in a closed, slightly inclined horizontal pipe with a modified RELAP5 code

The performance of the RELAP5 thermal-hydraulic system code was analyzed in predicting very fast transient condensation processes in horizontal pipes. The code significantly underpredicted the heat transfer from the primary to the secondary side in case ...
Prasser, Horst-Michael, Freixa Terradas, Jordi, Szijártó, Rita   +2 more
core  

Some of the next articles are maybe not open access.

Related searches:

Validation of neutronics and thermal-hydraulics coupling model of the RELAP5-3D code using the MSRE reactivity insertion tests

Nuclear Engineering and Design, 2022
Hiroyasu Mochizuki
exaly