Effect of Outside Cooling on the Thermal Behavior of a Pressurized Water Reactor Vessel Lower Head-Reference-Cited by-同舟云学术

Effect of Outside Cooling on the Thermal Behavior of a Pressurized Water Reactor Vessel Lower Head

Published:1992-12 Issue:3 Volume:100 Page:331-346
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Park Hyunjae¹,Dhir Vijay K.¹

Affiliation:

1. University of California-Los Angeles School of Engineering and Applied Science Mechanical, Aerospace and Nuclear Engineering Department Los Angeles, California 90024

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT92-A34729

Reference14 articles.

1. Bwr Owner’s Group, “Emergency Procedure Guidelines,” Rev. 4, Topical Report NEDO-31331, General Electric Company (Mar. 1987).

2. W. A. CONDON, S. R. GREENE, R. M. HARRINGTON, and S. A. HODGE, “SBLOCA Outside Containment at Browns Ferry Unit One —Accident Sequence Analysis,” NUREG/CR-2672, Vol.1, p. 197, ORNL/TM-8119/V1, U. S. Nuclear Regulatory Commission, (1982)

3. S. A. HODGE, J. C. CLEVELAND, and T. S. KRESS, “External Flooding of a BWR Reactor Vessel as a Late Accident Mitigation Strategy,” ORNL/NRC/LTR-91/9, Oak Ridge National Laboratory (Aug. 27, 1991).

4. R. M. OSTMEYER, “An Approach to Treating Radionuclide Decay Heating for Use in the MELCOR Code System,” NUREG/CR-4169, U. S. Nuclear Regulatory Commission (1985).

5. J. METZINGER and H. V. KLAPDOR, “New Results on the Decay Heat of Nuclear Reactors,” Max-Planck-Institut für Kernphysik (1985).

Cited by 21 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. A review on the external cooling of the pressure vessel lower head in nuclear power plant;Nuclear Engineering and Design;2023-08

2. External Cooling of Reactor Vessels during Severe Accident;Multiphase Flow Dynamics 5;2015

3. A simple novel and fast computational model for the LIVE-L4;Progress in Nuclear Energy;2013-09

4. External cooling of reactor vessels during severe accident;Multiphase Flow Dynamics 5;2011

5. An approach to numerical simulation and analysis of molten corium coolability in a boiling water reactor lower head;Nuclear Engineering and Design;2010-09