Peach Bottom 2 Turbine Trip Simulation Using TRAC-BF1/COS3D, a Best-Estimate Coupled 3-D Core and Thermal-Hydraulic Code System-Reference-Cited by-同舟云学术

Peach Bottom 2 Turbine Trip Simulation Using TRAC-BF1/COS3D, a Best-Estimate Coupled 3-D Core and Thermal-Hydraulic Code System

Published:2004-10 Issue:2 Volume:148 Page:281-290
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Ui Atsushi¹,Miyaji Takamasa¹

Affiliation:

1. Nuclear Fuel Industries, Ltd. Fuel Engineering and Development Department 3135-41, Muramatsu, Tokai-mura Naka-gun, Ibaraki 319-1196, Japan

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE04-A2458

Reference5 articles.

1. “Three-Dimensional BWR Core Simulation Method,” Nuclear Fuel Industries, Ltd., NLR-03 (Apr. 1994) (in Japanese).

2. “Core Management System for BWR Nuclear Power Plants,” Nuclear Fuel Industries, Ltd., NLR-20 (Mar. 1999) (in Japanese).

3. N. H. LARSEN, “Core Design and Operating Data for Cycle 1 and 2 of Peach Bottom 2,” EPRI NP-563, Electric Power Research Institute (June 1978).

4. L. A. CARMICHAEL and R. O. NIEMI, “Transient and Stability Tests at Peach Bottom Atomic Power Station Unit 2 at End of Cycle 2,” EPRI NP-564, Electric Power Research Institute (June 1978).

5. J. S. SOLIS et al. “Boiling Water Reactor Turbine Trip (TT) Benchmark Volume I: Final Specifications,” NEA/NSC/DOC(2001)1, Rev. 1, Nuclear Energy Agency (Oct. 2001).

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