Science and Technology of Nuclear Installations

Severe Accident Analysis in Nuclear Power Plants


Publishing date
01 May 2012
Status
Published
Submission deadline
01 Nov 2011

1Departamento de Procesos e Hidráulica, Universidad Autónoma Metropolitana-Iztapalapa, 09340 México, DF, Mexico

2Departamento de Física e Ingeniería Nuclear, Universitat Politècnica de Catalunya, 08028 Barcelona, Spain

3National Commission of Nuclear Safety and Safeguards (CNSNS), 03020 México, DF, Mexico


Severe Accident Analysis in Nuclear Power Plants

Description

Safety at a nuclear power plant is essential, and safety standards are constantly reviewed and upgraded as new developments and research are performed. Constant research regarding this subject is fundamental for the nuclear industry.

Although severe accident analysis and research has been performed throughout the evolution of nuclear industry, it has not yet considered all plausible scenarios. Adequate analyses are needed for all phases of this matter in order to maintain or improve safety margins. Hence it is essential to encourage researchers to keep performing and developing research, codes, and simulations of these potentially dangerous events.

This is why we invite researchers to contribute with original works in an effort to improve nuclear safety and severe accident guidelines. We are interested in articles which can help improve safety in existing generation II nuclear power plants (NPP) as well as in generation III NPP being built and in generation III+ and IV NPP being developed. Potential topics include, but are not limited to:

  • Core chemical reactions and behavior
  • Core heat-up, degradation or damage, decay heat removal, and postaccident heat removal
  • Cool-ability of severely damaged core in the reactor vessel
  • Hydrogen generation, deflagration to detonation transition (DDT), and flame acceleration (FA)
  • Status of severe accident management guidelines (SAMGs)
  • Accident frequency analysis and probabilistic risk assessment
  • Core and contention damage mitigation analysis
  • Corium stabilization in reactor vessel/in containment
  • Severe accident code assessment, validation, and application
  • Containment loads and structural response
  • Analysis of boron injection/dilution
  • Experimental investigations in severe accidents
  • Fuel degradation in the spent fuel pool
  • Fission products behaviors and source term evaluation

Before submission authors should carefully read over the journal's Author Guidelines, which are located at http://www.hindawi.com/journals/stni/guidelines/. Prospective authors should submit an electronic copy of their complete manuscript through the journal Manuscript Tracking System at http://mts.hindawi.com/ according to the following timetable:


Articles

  • Special Issue
  • - Volume 2012
  • - Article ID 430471
  • - Editorial

Severe Accident Analysis in Nuclear Power Plants

Gilberto Espinosa-Paredes | Lluís Batet | ... | Jun Sugimoto
  • Special Issue
  • - Volume 2012
  • - Article ID 646327
  • - Research Article

Preliminary Assessment of the Possible BWR Core/Vessel Damage States for Fukushima Daiichi Station Blackout Scenarios Using RELAP/SCDAPSIM

C. M. Allison | J. K. Hohorst | ... | R. Lopez
  • Special Issue
  • - Volume 2012
  • - Article ID 305405
  • - Research Article

Simulation of the Lower Head Boiling Water Reactor Vessel in a Severe Accident

Alejandro Nuñez-Carrera | Raúl Camargo-Camargo | ... | Adrián López-García
  • Special Issue
  • - Volume 2012
  • - Article ID 487371
  • - Research Article

Failure Assessment Methodologies for Pressure-Retaining Components under Severe Accident Loading

J. Arndt | H. Grebner | J. Sievers
  • Special Issue
  • - Volume 2012
  • - Article ID 656590
  • - Research Article

Response Analysis on Electrical Pulses under Severe Nuclear Accident Temperature Conditions Using an Abnormal Signal Simulation Analysis Module

Kil-Mo Koo | Jin-Ho Song | ... | Gyu-Tae Kim
  • Special Issue
  • - Volume 2012
  • - Article ID 209420
  • - Research Article

Severe Accident Simulation of the Laguna Verde Nuclear Power Plant

Gilberto Espinosa-Paredes | Raúl Camargo-Camargo | Alejandro Nuñez-Carrera
  • Special Issue
  • - Volume 2012
  • - Article ID 620298
  • - Review Article

Station Black-Out Analysis with MELCOR 1.8.6 Code for Atucha 2 Nuclear Power Plant

Analia Bonelli | Oscar Mazzantini | ... | Marcelo Gimenez
  • Special Issue
  • - Volume 2012
  • - Article ID 735719
  • - Research Article

An Evaluation Methodology Development and Application Process for Severe Accident Safety Issue Resolution

Robert P. Martin
  • Special Issue
  • - Volume 2012
  • - Article ID 878174
  • - Research Article

Heat and Mass Transfer during Hydrogen Generation in an Array of Fuel Bars of a BWR Using a Periodic Unit Cell

H. Romero-Paredes | F. J. Valdés-Parada | G. Espinosa-Paredes
  • Special Issue
  • - Volume 2012
  • - Article ID 943197
  • - Research Article

Large-Scale Containment Cooler Performance Experiments under Accident Conditions

Ralf Kapulla | Guillaume Mignot | Domenico Paladino
Science and Technology of Nuclear Installations
 Journal metrics
Acceptance rate32%
Submission to final decision60 days
Acceptance to publication39 days
CiteScore1.700
Impact Factor0.825
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