The discovery of fission is roughly seven decades old, and the potential for large-scale power production from fission is now well established. Currently, nearly 430 nuclear power plants (NPPs) produce electricity around the globe contributing to around 11.2% of the total electricity production. With the present concern over the green house gas generation by burning fossil fuel and the rapid growth of electricity generation capacity in Asian and African nations, particularly in China and India, nuclear power capacity is expected to grow substantially in the near future. Among the operating nuclear power plants (NPPs), the water-cooled designs are the dominant ones due to simplicity in their design and economic competitiveness. After 25 years of Chernobyl accident when resurgence in the nuclear power program worldwide was imminent, the accident at Fukushima gave a serious blow to the confidence in nuclear safety, particularly under conditions of extreme natural disasters, such as earthquake...
Skip Nav Destination
Article navigation
April 2017
Guest Editorial
Special Section: Pressurized Heavy Water Reactors Safety
S. Banerjee,
S. Banerjee
Guest Editor
Homi Bhabha Chair Professor
Bhabha Atomic Research Centre,
Trombay,
Mumbai 400 085, India
Homi Bhabha Chair Professor
Bhabha Atomic Research Centre,
Trombay,
Mumbai 400 085, India
Search for other works by this author on:
A. K. Nayak,
A. K. Nayak
Guest Editor
Reactor Engineering Division,
Bhabha Atomic Research Centre,
Trombay,
Mumbai 400 085, India
Reactor Engineering Division,
Bhabha Atomic Research Centre,
Trombay,
Mumbai 400 085, India
Search for other works by this author on:
T. (Nithy) Nitheanandan
T. (Nithy) Nitheanandan
Guest Editor
Fuel and Fuel Channel Safety Branch,
Canadian Nuclear Laboratories,
Chalk River, ON K0J 1J0, Canada
Fuel and Fuel Channel Safety Branch,
Canadian Nuclear Laboratories,
Chalk River, ON K0J 1J0, Canada
Search for other works by this author on:
S. Banerjee
Guest Editor
Homi Bhabha Chair Professor
Bhabha Atomic Research Centre,
Trombay,
Mumbai 400 085, India
Homi Bhabha Chair Professor
Bhabha Atomic Research Centre,
Trombay,
Mumbai 400 085, India
A. K. Nayak
Guest Editor
Reactor Engineering Division,
Bhabha Atomic Research Centre,
Trombay,
Mumbai 400 085, India
Reactor Engineering Division,
Bhabha Atomic Research Centre,
Trombay,
Mumbai 400 085, India
T. (Nithy) Nitheanandan
Guest Editor
Fuel and Fuel Channel Safety Branch,
Canadian Nuclear Laboratories,
Chalk River, ON K0J 1J0, Canada
Fuel and Fuel Channel Safety Branch,
Canadian Nuclear Laboratories,
Chalk River, ON K0J 1J0, Canada
ASME J of Nuclear Rad Sci. Apr 2017, 3(2): 020301 (2 pages)
Published Online: March 1, 2017
Article history
Received:
January 13, 2017
Revised:
January 16, 2017
Citation
Banerjee, S., Nayak, A. K., and Nitheanandan, T. (. (March 1, 2017). "Special Section: Pressurized Heavy Water Reactors Safety." ASME. ASME J of Nuclear Rad Sci. April 2017; 3(2): 020301. https://doi.org/10.1115/1.4035852
Download citation file:
104
Views
Get Email Alerts
Cited By
Editorial
ASME J of Nuclear Rad Sci (January 2025)
Greeting From the President-Elect of JSME
ASME J of Nuclear Rad Sci (January 2025)
Operation Optimization Framework for Advanced Reactors Using a Data-Driven Digital Twin
ASME J of Nuclear Rad Sci (April 2025)
Numerical Analysis of Gas Generation and Migration in a Radioactive Waste Disposal Cell of a Deep Geological Repository
ASME J of Nuclear Rad Sci (April 2025)
Related Articles
Analyses of Feedwater Trip With SBO Sequence of VVER1000 Reactor
ASME J of Nuclear Rad Sci (October,2016)
Experimental Study on Melt Coolability Capability of Calandria Vault Water During Severe Accident in Indian PHWRs for Prolonged Duration
ASME J of Nuclear Rad Sci (July,2018)
Experimental Demonstration of Safety of AHWR during Stagnation Channel Break Condition in an Integral Test Loop
ASME J of Nuclear Rad Sci (April,2018)
In-Calandria Retention of Corium in PHWR: Experimental Investigation and Remaining Issues
ASME J of Nuclear Rad Sci (April,2017)
Related Proceedings Papers
Related Chapters
Insights and Results of the Shutdown PSA for a German SWR 69 Type Reactor (PSAM-0028)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Design of Indian Pressurized Heavy Water Reactors
Global Applications of the ASME Boiler & Pressure Vessel Code
Safety
Engineering the Everyday and the Extraordinary: Milestones in Innovation