Results 111 to 120 of about 362 (143)

?????????????????? ?????????????????????????????????????? ???????????? ???????????????? ????????-1000 ?????? ?????????????????????????? ???????? RELAP5/MOD3.2 ???? ???????????? ?????????????? ?????????????????? ?????????????? ????????????????

2016
The WWER-1000 reactor model for RELAP5/mod3.2 computer code is validated. The model includes detailed modeling of the downcomer by dividing it azimuthally into 20 vertical channels with crossflow junctions. The measured parameters for the failure of the Rivne-3 pressurizer safety valve to close are used as experimental data.
openaire   +3 more sources

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

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

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

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

?????????????????????? ???????????????? ?????????????????? ???????? 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

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

Application of Relap5-3D© and Relap5/mod3.2.2 to Phase I of OECD PWR MSLB Benchmark

2001
Pioneering results obtained at University of Pisa related to the analyses of the Three Mile Island (TMI-Unit-1) Benchmark involving the coupling between thermal-hydraulics and 3-D neutron physics codes (see previous research products), were submitted to the attention of the scientific community.
Spadoni Antonino, D’Auria F., Hassan Yassin   +2 more
openaire   +1 more source

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

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

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

Annals of Nuclear Energy, 2020
C Allison
exaly  

RELAP5 Assessment Using ISP38 Data

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

Assessment and modifications of the post-CHF wall heat transfer packages of RELAP5/MOD2.5 and RELAP5/MOD3

1993
During the last few months, considerable effort has been spent on assessing the post-CHF wall heat transfer package of RELAP5/MOD3/v7j (R5M3) as well as on investigating the effect of some model differences between this code and its predecessor, RELAP5/MOD2.S (R5M2).
openaire   +1 more source