Science and Technology of Nuclear Installations

Advanced PHWR Safety Technology: PHWR Challenging Issues for Safe Operation and Long-Term Sustainability


Status
Published

Lead Editor

1Korea Atomic Energy Research Institute, Daejeon, Republic of Korea

2Canadian Nuclear Safety Commission, Ottawa, Canada

3Atomic Energy of Canada Limited-Chalk River Lab, Ottawa, Canada

4Atomic Energy Research Institute, Daejeon, Republic of Korea

5The Institute of Applied Energy, Minato, Japan


Advanced PHWR Safety Technology: PHWR Challenging Issues for Safe Operation and Long-Term Sustainability

Description

Pressurized heavy water reactor (PHWR) has been operated world-widely as one of the most efficient and flexible nuclear reactor owing to its superior neutron efficiency and flexibility to consider broad range of alternative fuel cycles depending on individual national interest. Also, it has been recognized as a safe reactor because of its inherent safety features and special safety systems such as two independent shutdown systems, emergency core cooling system, and containment system. However, with the current rising expectations for the life extension of the old reactors closing to its lifetime together with recent enhancement for safer operation after the Fukushima accident, it is a very appropriate time to review and communicate knowledge and information for the advanced and enhanced PHWR safety technologies.

We invite investigators to contribute original research articles as well as review articles that will share the advanced PHWR safety technology which can help to overcome the challenging issues for safe operation and long-term sustainability of PHWR. We also welcome submissions from investigators that address their own valuable research works.

Potential topics include, but are not limited to:

  • Safety analysis, thermal-hydraulic, and reactor physics for PHWR
  • Severe accident, stress test, and PSA for PHWR
  • Aging and plant life management, continued operation for PHWR
  • Fuel performance and manufacturing technology for PHWR

Articles

  • Special Issue
  • - Volume 2016
  • - Article ID 2689861
  • - Editorial

Advanced PHWR Safety Technology: PHWR Challenging Issues for Safe Operation and Long-Term Sustainability

Jin Ho Song | Wei Shen | ... | Masanori Naitoh
  • Special Issue
  • - Volume 2016
  • - Article ID 5903602
  • - Research Article

Scaled-Down Moderator Circulation Test Facility at Korea Atomic Energy Research Institute

Hyoung Tae Kim | Bo Wook Rhee
  • Special Issue
  • - Volume 2015
  • - Article ID 143767
  • - Review Article

CANDU Safety R&D Status, Challenges, and Prospects in Canada

W. Shen | F. Doyle
  • Special Issue
  • - Volume 2015
  • - Article ID 520756
  • - Research Article

Safety Enhancements for PHWRs Based on Macroscopic Losses of the Fukushima Accident

Sang Ho Kim | Tsuneo Futami | ... | Yong Hoon Jeong
  • Special Issue
  • - Volume 2015
  • - Article ID 439863
  • - Research Article

Measurement of Velocity and Temperature Profiles in the 1/40 Scaled-Down CANDU-6 Moderator Tank

Hyoung Tae Kim | Jae Eun Cha | ... | In Cheol Bang
  • Special Issue
  • - Volume 2015
  • - Article ID 571547
  • - Research Article

The Effects of the Treatment of the Periodic Boundary Condition in TRIAINA Codes with a Pressure Tube Creep Problem

E. H. Ryu | S. Y. Yoo | ... | J. Y. Jung
  • Special Issue
  • - Volume 2015
  • - Article ID 284642
  • - Research Article

Monte Carlo Few-Group Constant Generation for CANDU 6 Core Analysis

Seung Yeol Yoo | Hyung Jin Shim | Chang Hyo Kim
  • Special Issue
  • - Volume 2015
  • - Article ID 243867
  • - Research Article

CHF Enhancement of Advanced 37-Element Fuel Bundles

Joo Hwan Park | Jong Yoeb Jung | Eun Hyun Ryu
  • Special Issue
  • - Volume 2015
  • - Article ID 462941
  • - Research Article

Uncertainty Analysis of the Potential Hazard of MCCI during Severe Accidents for the CANDU6 Plant

Sooyong Park | Kwang-Il Ahn | YongMann Song
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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