Results 11 to 20 of about 2,651,698 (166)
Validation of RELAP5 MOD3.3 code for Hybrid-SIT against SET and IET experimental data
Nuclear Engineering and Technology, 2020 We validated the performance of RELAP MOD3.3 code regarding the hybrid SIT with available experimental data. The concept of the hybrid SIT is to connect the pressurizer to SIT to utilize the water inside SIT in the case of SBO or SB-LOCA combined with ...
Ho Joon Yoon +3 more
doaj +3 more sources
Nuclear Engineering and Technology, 2018 An experiment was conducted for the OECD/NEA ROSA-2 Project using the large-scale test facility (LSTF), which simulated a 17% hot leg intermediate-break loss-of-coolant accident in a pressurized water reactor (PWR).
T. Takeda, I. Ohtsu
semanticscholar +3 more sources
Development and Assessment of the COBRA/RELAP5 Code. [PDF]
Journal of Nuclear Science and Technology, 1997 The COBRA/RELAP5 code has been developed to combine the realistic three-dimensional reactor vessel model of COBRA-TF with RELAP5/MOD3.2, thus to produce an advanced system analysis code with a multidimensional thermal-hydraulic module. This paper provides the integration scheme of the two codes. The results of developmental assesments are also provided,
Jae-Jun JEONG, Suk Ku SIM, Sang Yong LEE
openaire +1 more source
He jishu, 2022 BackgroundThe natural circulation chloride cooled fast reactor (N3CFR) has the characteristics of simple structure, high inherent safety and good economy. It is an advanced fourth-generation nuclear energy system with development potential.
SONG Shiyang +3 more
doaj +1 more source
Study on the Density Wave Instability in Natural Circulation System under Rolling Conditions
International Journal of Energy Research, Volume 2023, Issue 1, 2023., 2023 In the ocean environment, the thermal fluid system installed on the ship moves with the waves. This unsteady transient motion imposes additional body forces on the liquid. Thereby, the thermohydraulic properties of the thermal fluid system are changed, especially for natural circulation systems with a low driving force.
Houjun Gong +6 more
wiley +1 more source
He jishu, 2021 BackgroundThe liquid-fueled molten salt reactor (MSR) is one of the Generation IV advanced reactor concepts, which has unique advantages in aspects of safety, economy and nonproliferation.
LI Rui, CHENG Maosong, DAI Zhimin
doaj +1 more source
SCDAP/RELAP5/MOD2 code manual [PDF]
, 1989 The SCDAP/RELAP5 code has been developed for best-estimate transient simulation of light water reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system, the core, and the fission products and aerosols in the system during a severe accident transient as well as large and small break loss-of ...
Allison, C. M. +13 more
openaire +6 more sources
Science and Technology of Nuclear Installations, Volume 2023, Issue 1, 2023., 2023 This paper summarises the results of an experimental campaign carried out at SIET on the ELSMOR facility built in 2022 to validate a decay heat removal system for the E‐SMR. Based on the passive mechanisms of natural circulation, the system aims to dissipate the reactor decay heat to a water pool, using two heat exchangers: a plate‐type one coupling ...
Roberta Ferri +8 more
wiley +1 more source
SCDAP/RELAP5/MOD2 code manual [PDF]
, 1990 This report describes the materials properties correlations and computer subcodes (MATPRO) developed for use with various light water reactor (LWR) accident analysis computer programs. Formulation of the materials properties are generally semiempirical in nature.
Hohorst +5 more
openaire +2 more sources