Results 151 to 160 of about 5,521 (168)

One-Dimensional Diffusion Theory Kinetics in RELAP5

Nuclear Science and Engineering, 1995
A one-dimensional (axial) space-time reactor kinetics capability has been developed for the well-known RELAP5 thermohydraulic systems code for modeling the behavior of nuclear power plants. The method is based on the analytic nodal method with a novel technique for performing the temporal integration over relatively large time steps.
William K. Terry, David W. Nigg
openaire   +1 more source

?????????????????? ?????????????????????????????????????? ???????????? ???????????????? ????????-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

???????????? ???????????? ???????????? ?????????????????????? ????????-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

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

RELAP5/mod3.2 - QUABOX/CUBBOX-HYCA Coupling

1998
abstract to be ...
Čavlina, Nikola, Špalj, Srđan, Pevec, Dubravko, Grgić, Davor, Bajs, Tomislav   +4 more
openaire   +1 more source

QUENCH-06 RELAP5/SCDAPSIM Nodalization Notebook

2003
N ...
openaire   +1 more source