Explanipedia

Benchmarking study of ASYST code against CORA-18 BWR experiment with integrated uncertainty analysis Open

Rawan Mustafa, Heriberto Sánchez Mora, C.M. Allison, Raimon Pericas, Yahya A. Alzahrani , et al. · 2025

Benchmarking Study of Asyst Code Against Cora-18 Bwr Experiment with Integrated Uncertainty Analysis Open

Rawan Mustafa, Heriberto Sánchez–Mora, C.M. Allison, Raimon Pericas, Yahya A. Alzahrani , et al. · 2025

Investigation of computational model for the natural circulation at dual channel facility Open

Marwa A. Shewita, Ebrahiem Ebrahiem, C.M. Allison, Moustapha Salem Mansour, Ayah E. Elshahat , et al. · 2024

DIFFERENT NUMERICAL MODELING APPROACHES APPLIED TO RELAP/SCDAPSIM CODE FOR THE SIMULATION OF QUENCH-20 TEST Open

Noura Elsalamouny, Tadas Kaliatka, C.M. Allison · 2023

In 2019 KIT conducted the latest quench test (QUENCH-20 test) which was equipped with a BWR fuel bundle to investigate the hydrogen source and B4C reactions during severe accident conditions. Currently, LEI is modeling the QUENCH-20 test b…

Rhys Simulation of Uniform Heating of Natural Circulation Inside Prismatic Modular Reactors Open

Marwa Abozeid Shewitah, C.M. Allison, Ibrahim Ismail Ibrahim, Moustapha Salem Mansour, Ayah E. Elshahat , et al. · 2023

Relap/Scdapsim and Asyst Ver 3 Fukushima Related Activities Open

Raimon Pericas, C.M. Allison, Judy K. Hohors, Alex Ezzidi Nakata · 2023

Uncertainty Study of the In-Vessel Phase of a Severe Accident in a Pressurized Water Reactor Open

Siniša Šadek, Davor Grgić, C.M. Allison, Marina Pérez-Ferragut · 2022

A comprehensive uncertainty analysis in the event of a severe accident in a two-loop pressurized water reactor is conducted using an uncertainty package integrated in the ASYST code. The plant model is based on the nuclear power plant (NPP…

NEED OF A NEXT GENERATION SEVERE ACCIDENT CODE Open

Alexandre Ezzidi Nakata, Masanori Naitoh, C.M. Allison · 2019

Two international severe accident benchmark problems have been performed recently by using several existing parametric severe accident codes: The Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Plant (BSAF) and the B…

HIGHLIGHTS OF THE INTEGRATED UNCERTAINTY ANALYSIS OF THE CORA 28 BWR EXPERIMENT USING RELAP/SCDAPSIM/MOD3.4 WITH IUA Open

Ramadan J. Mustafa, Tianyang Bao, C.M. Allison, J. K. Hohorst · 2019

RELAP/SCDAPSIM, a detailed system thermal hydraulic code with best estimate fuel behavior and severe accident models and correlations, is being developed by Innovative Systems Software with support from an international group of users, uni…

Development and Benchmarking of Mechanistic Channel Deformation Models in RELAP/SCDAPSIM/MOD3.6 for CANDU Severe Accident Analysis Open

Feng Zhou, D. R. Novog, L.J. Siefken, C.M. Allison · 2018

In different stages of postulated severe accidents in CANDU reactors, the fuel channels may experience a series of thermomechanical deformations, some of which may have significant impacts on accident progression; however, they have not be…

Modeling and simulation of the QUENCH 12 experiment with the RELAP/SCDAPSIM/MOD3.5 code Open

Gergana Gerova, Ivan Spasov, C.M. Allison, M. Steinbrück · 2018

This paper presents a RELAP/SCDAPSIM MOD3.5 model of the QUENCH 12 experiment. The model uses the new heater rod model and automatic time advancement in the simulation of experiment and it is based on the basis Innovative Systems Software’…

RELAP/SCDAPSIM/MOD3.5 analysis of KIT's QUENCH-14 experiment Open

Olga Dutkiewicz, Krzysztof M. Marcinkiewicz, Hiroshi Madokoro, Siarhei Shumski, C.M. Allison , et al. · 2017

\nThe QUENCH-14 experiment was performed within the ACM series (Advanced Cladding Materials) performed by “Karlsruhe Institute of Technology” (KIT), Germany, to investigate the performance of M5® cladding material. During the experiment th…

Assessment of RELAP/SCDAPSIM/MOD3.4 Prediction Capability with Severe Fuel Damage Scoping Test Open

Noppawan Rattanadecho, Somboon Rassame, Kampanart Silva, C.M. Allison, J. K. Hohorst · 2017

The Power Burst Facility (PBF) was designed to provide experimental data to determine the thresholds for failure during accident conditions. Thus, the PBF benchmark using severe accidental analysis codes is essential to designing reactor f…

ICONE23-1623 THE DEVELOPMENT OF RELAP/SCDAPSIM/MOD4.0 FOR ADVANCED FLUID SYSTEMS DESIGN ANALYSIS Open

Mercedes Pérez, C.M. Allison, Rozenn Wagner, Veronica Martinez, Zheng Yi Fu , et al. · 2015

The RELAP/SCDAPSIM/MOD4.0 code is being developed as part of the international SCDAP Development Training Program (SDTP). SDTP consists of more than 90 organizations in 30 countries supporting the development of technology, software, and t…

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