Results 151 to 160 of about 2,939 (182)

?????????????????? ???????????????????????? ?????????????????? ?????????????????? ?????????????????????????? ?????????????????????????????? ?????????????? ???????????????????? ???????????????????? ???????????????? ???????? ???????????????? ?? ?????????????????? ???????????????? ???????????? ?????? ???????????? ???????? RELAP5

2016
?????????????????? ?????????????????????????? ???????????????????????????? ???????? ?????? ?????????????????????????? ???????? RELAP5/MOD3.2, ???? ?????????????????? ???????????????? ?????????????????????????? ?????????????????????????? ?????? ???????????? ?? ?????????????????? ?? ?????????????????? ?????????????? ?? ?????????????????????? ???? ????????
openaire   +1 more source

?????????????????????????? ???????????????????????????? ???????????????????? ?? ?????????????? ???????????????????????????? ???????????????????????? ?????? ???????????????????????? ???????????????????? ?????????????????????????? ?????????????? ?????????????? ?????? ???????????? ?????????????????? ?????????????? ???????????????? ?? ?????????????? ???????? RELAP5/MOD3.2

2016
?????????????????? ?????????????????? ???????????????? ?? ?????????????? ?????????? ???????????? ???????????????? ????????-1000 ?????? ?????????????????????????? ???????? RELAP5/MOD3.2 ???? ?????? ???????????? ???? ???????????? ?????? ?????????????????????????? ???????????????????????????????????? ?????????????? ?? ?????????????? ???????????????????????
openaire   +1 more source

RELAP5 Simulations of the PASI Experiment on Containment Wall Condensation

2024 International Congress on Advances in Nuclear Power Plants (ICAPP)
During a Design Basis Accident (DBA) or Beyond Design Basis Accident (BDBA) scenario, concerning a Loss Of Coolant Accident (LOCA), the heat extraction from the containment is related to the steam condensation on the cold surfaces, thermosiphon cooling loop and through the connection to the water tank.
Grippo G., Polidori M.
openaire   +2 more sources

?????????????????????? ???????????????? ?????????????????? ???????? RELAP5 ?????? ?????????????????????? ?? ?????????????????? ????????-440

2017
The results of standard problem realization are presented for RELAP5 code validation based on documented Plant data about primary to secondary leak accident occurred at VVER-440 Reactor Unit. Thermalhydraulic model as well as comparative analysis of transient progression are described.
openaire   +1 more source

???????????? ???????????? ???????????? ?????????????????????? ????????-1000 c ???????????????????????? ?????????????????????? ??????????-???????????????? ?????????????? ?????????????? ?? ???????????? ???????????????????? ?????????????????????? ???????????????? ?????? ?????????????????? ???????? RELAP5

2017
???????????????? ???????????????? ???????????????????? ?????????????????? ???????????????????? ???????? RELAP5 ?? ???????????? ???????????????????????????? ???????????????????????????? ???????????????????????? ?????????????? ?? ???????????????? ?????? ???????????????????? ?????????????????????? ???????????????? ?????? ????????-1000 ?????????????????????
openaire   +1 more source

RELAP5 Assessment Using ISP38 Data

2002
tt
Šegon, Velimir, Debrecin, Nenad, Čavlina, Nikola   +2 more
openaire   +1 more source

Linear stability analysis of RELAP5 two-fluid model in nuclear reactor safety results

Annals of Nuclear Energy, 2020
P Munshi, C Allison
exaly  

Assessment of RELAP5/MOD3.2 for simulating density wave oscillation with a two-phase natural circulation test facility

Nuclear Engineering and Design, 2021
Haijun Jia
exaly  

Assessment of a RELAP5 model for the IPR-R1 TRIGA research reactor

Annals of Nuclear Energy, 2010
Antonella L Costa, Claubia Pereira, Amir Z Mesquita   +2 more
exaly  

Preliminary validation of RELAP5/Mod4.0 code for LBE cooled NACIE facility

Nuclear Engineering and Design, 2017
Ashok Khanna
exaly