Results 171 to 180 of about 1,365 (205)

???????????? ???????????? ???????????? ?? ?????????????? ???????????????? ?????????????????????????????? ???????????????? ???????????? ?????? "????????????????-??????????" ?? ?????????????????????????? ???????????????????????????? ???????? MELCOR 1.8.6

2018
???????????????????????? ?????????????? ???? ?????????????????????? ?????????????? ???????????????? (????) ?????? ???????????????????????? ???????? ?????? ??????????????????-???????????? ???? ???????????????????? ?????????????????????????????????? ?????????????????????? ?????????????????? ???????????? ???????????? ?? ????, ???????????????? ?? ??????????
openaire   +1 more source

?????????????? ?????????? ???????????????????????? ?? ???????????????????????????? ???? ???????????????? ???????????????????? ?????????????????? ???????????????????? ?????????????????? ???????????????????????? ?? ?????????????? ???????? Melcor

2016
This paper focuses on modeling of the nuclear steam supply system (NSSS) with use of the MELCOR computer code. Two models of NSSS with a steam generator presented as one and three volumes are compared. The volume of the steam generator is divided to evaluate the effect of recirculation of the secondary steam-and-water mixture on the processes that ...
openaire   +1 more source

?????????????????????? ?????????????????????????? ???????????????? ???????????????? ?????????????????????????? ???????????????? ?????????????? ?? ???????????????????????????? ???????????????????? ???????? MELCOR 1.8.5

2016
???????????????? ???????????? ???????????????????? ???????????????? ?? ?????????????? ???????????????? (????) ?????????????????????????????? ???????????????? ???????????? ?? ?????????????? ?????????????????????? ???? ?? ?????????????????????????? ??????????????????????????? ???????? MELCOR 1.8.5 ???? ?????????? ?????? ?????????????????? BWR ?? PWR. ????
openaire   +1 more source

MELCOR Overview Introduction .

Proposed for presentation at the EFCOG Nuclear & Facility Safety Workshop Spring 2022 held February 15-24, 2022 in Washington, DC United States, 2022
David Luxat, David Louie, Larry Humphries   +2 more
openaire   +1 more source

MELCOR Hydrodynamics.

Proposed for presentation at the EFCOG Nuclear & Facility Safety Workshop Spring 2022 held February 15-24, 2022 in Washington, DC United States, 2022
openaire   +1 more source

???????????? ?????????????? ???????????? ?? ???????????????? ???????????????? ?????????????????????????? ?????????????? ?????? ?????????????????????? ????????-1000 ?????? ???????????? ???????????????????? ???????? MELCOR 1.8.5

2016
The spent fuel pool model for computer code MELCOR 1.8.5 is developed for WWER- 1000 units. The initiating event involving loss of heat removal from the spent fuel pool is analyzed. Time frames of fuel damage, hydrogen generated mass and radiation consequences are estimated.
openaire   +1 more source

Reactor Vessel Modelling with the MELCOR Code

2019
MELCOR is an integral severe accident code that enables calculation of complete transient sequence in a reactor coolant system (RCS), nuclear power plant (NPP) secondary side and the containment. NPP modelling with the MELCOR code provides the user freedom to develop its own modelling approach by following general guidelines determined by code ...
Šadek, Siniša, Grgić, Davor, Vuković, Franjo, Benčik, Vesna   +3 more
openaire   +2 more sources

MELCOR-TMAP: The integration of MELCOR for fusion and TMAP4 for fusion reactor systems safety analysis and tritium inventory tracking

Fusion Engineering and Design, 2023
Matthew Eklund, Adriaan Riet
exaly  

ORIGEN/MELCOR Integration

MELCOR Code Assessment Program - Bethesda, MD, Maryland, United States of America - June - 2023, 2023
openaire   +1 more source

MELCOR for HTGR Applications.

Proposed for presentation at the NURETH-19 held March 7-February 11, 2022 in Brussels, Belgium, 2022
openaire   +1 more source