The Development of the Fast-Running Simulation Pressurized Water Reactor Plant Analyzer Code (NUPAC-1)-Reference-Cited by-同舟云学术

The Development of the Fast-Running Simulation Pressurized Water Reactor Plant Analyzer Code (NUPAC-1)

Published:1989-06 Issue:3 Volume:85 Page:259-273
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Sasaki Kazunori¹,Terashita Naotaka¹,Ogino Takamichi¹

Affiliation:

1. Mitsubishi Electric Corporation Central Research Laboratory, 1-1, Tsukaguchi-Honmachi 8-chome, Amagasaki, Hyogo, 661 Japan

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/NT89-A34248

Reference5 articles.

1. A semi-implicit method for two-phase fluid dynamics

2. “RETRAN-02, A Program for Transient Thermal-Hydraulic Analysis of Complex Fluid Flow Systems,” EPRI-NP-1850, Electric Power Research Institute (May 1981).

3. “RELAP-5/MOD2 Code Manual,” EGG-SAAM-6377, EG&G Idaho, Inc. (Apr. 1984).

4. “NRC Report on the January 25, 1982, Steam Generator Tube Rupture at R. E. Ginna Nuclear Power Plant,” NUREG-0909, U.S. Nuclear Regulatory Commission (Apr. 1982).

5. J. F. LIME and R. P. JENKS, “A TRAC-PF1/MOD1 Analysis of the Ginna Tube-Rupture Event on January 25, 1982,” NUREG/CR-4988, U.S. Nuclear Regulatory Commission (Oct. 1987).

Cited by 3 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. Development of High Precision Plant Simulator for Pressurized Water Reactor Plants using Distributed Architecture;Journal of Nuclear Science and Technology;1999-04

2. Recent advances in perturbative methods applied to nuclear engineering problems;Progress in Nuclear Energy;1998-01

3. Development of a Parallelism Analysis Integrated System for a Fast-Running Pressurized Water Reactor Plant Predictive Simulator;Nuclear Technology;1991-09