In this paper, the causes and the radiological consequences of the explosion of the Chernobyl reactor occurred at 1:23 a.m. (local time) on Apr. 26, 1986, and of the Fukushima Daiichi nuclear disaster following the huge Tsunami caused by the Great East Japan earthquake at 2.46 p.m. (local time) on Mar. 11, 2011 are discussed. The need for better severe accident management (SAM), and severe accident management guidelines (SAMGs), are essential in order to increase the safety of the existing and future operating nuclear power plants (NPPs). In addition to that, stress tests should, on a regular basis, be performed to assess whether the NPPs can withstand the effects of natural disasters and man-made failures and actions. The differences in safety preparations at the Chernobyl and Fukushima Daiichi will therefore be presented, as well as recommendations concerning improvements of safety culture, decontamination, and disaster planning. The need for a high-level national emergency response system in case of nuclear accidents will be discussed. The emergency response system should include fast alarms, communication between nuclear power plants, nuclear power authorities and the public people, as well as well-prepared and well-established evacuation plans and evacuation zones. The experiences of disaster planning and the development of a new improved emergency response system in Japan will also be presented together with the training and education program, which have been established to ensure that professional rescue workers, including medical staff, fire fighters, and police, as well as the normal populations including patients, have sufficient knowledge about ionizing radiation and are informed about the meaning of radiation risks and safety.
Skip Nav Destination
Article navigation
April 2018
Technology Review
Causes and Radiological Consequences of the Chernobyl and Fukushima Nuclear Accidents
L. Sihver,
L. Sihver
Technische Universität Wien,
Atominstitut,
Stadionallee 2,
Vienna 1020, Austria
e-mail: lembit.sihver@tuwien.ac.at
Atominstitut,
Stadionallee 2,
Vienna 1020, Austria
e-mail: lembit.sihver@tuwien.ac.at
Search for other works by this author on:
N. Yasuda
N. Yasuda
Research Institute of Nuclear Engineering,
University of Fukui,
Tsuruga-shi,
Fukui 914-0055, Japan
University of Fukui,
Tsuruga-shi,
Fukui 914-0055, Japan
Search for other works by this author on:
L. Sihver
Technische Universität Wien,
Atominstitut,
Stadionallee 2,
Vienna 1020, Austria
e-mail: lembit.sihver@tuwien.ac.at
Atominstitut,
Stadionallee 2,
Vienna 1020, Austria
e-mail: lembit.sihver@tuwien.ac.at
N. Yasuda
Research Institute of Nuclear Engineering,
University of Fukui,
Tsuruga-shi,
Fukui 914-0055, Japan
University of Fukui,
Tsuruga-shi,
Fukui 914-0055, Japan
1Corresponding author.
Manuscript received December 9, 2016; final manuscript received June 10, 2017; published online March 5, 2018. Assoc. Editor: Michal Kostal.
ASME J of Nuclear Rad Sci. Apr 2018, 4(2): 020914 (7 pages)
Published Online: March 5, 2018
Article history
Received:
December 9, 2016
Revised:
June 10, 2017
Citation
Sihver, L., and Yasuda, N. (March 5, 2018). "Causes and Radiological Consequences of the Chernobyl and Fukushima Nuclear Accidents." ASME. ASME J of Nuclear Rad Sci. April 2018; 4(2): 020914. https://doi.org/10.1115/1.4037116
Download citation file:
Get Email Alerts
Cited By
Investigating the Suitability of Cu2ZnSnS4 Thin Films for Gamma Radiation Dosimetry Applications in Nonmedical Environments
ASME J of Nuclear Rad Sci (April 2025)
Introduction to Nuclear Forensics Analysis Techniques
ASME J of Nuclear Rad Sci (January 2025)
Related Articles
Analyses of Feedwater Trip With SBO Sequence of VVER1000 Reactor
ASME J of Nuclear Rad Sci (October,2016)
Fukushima Unit 2 Accident Simulation With MELCOR 2.1
ASME J of Nuclear Rad Sci (April,2018)
The Fabulous Nuclear Odyssey of Belgium
J. Pressure Vessel Technol (June,2009)
Severe Accident Context Quantification for Long-Term Station Blackout in Boiling Water Reactor Nuclear Power Plants
ASME J of Nuclear Rad Sci (April,2018)
Related Proceedings Papers
Related Chapters
Czech & Slovakian Codes
Global Applications of the ASME Boiler & Pressure Vessel Code
Lessons Learned: NRC Experience
Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and Standards
QRAS Approach to Phased Mission Analysis (PSAM-0444)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)