Detailed CFX-5 study of the coolant mixing within the reactor pressure vessel of a VVER-1000 reactor during a non-symmetrical heat-up test-Reference-Cited by-同舟云学术

Detailed CFX-5 study of the coolant mixing within the reactor pressure vessel of a VVER-1000 reactor during a non-symmetrical heat-up test

Published:2008-03 Issue:3 Volume:238 Page:445-452
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Böttcher Michael

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference8 articles.

1. ANSYS CFX, Reference Guide, Release 10.0, 2005.

2. Barth, T.J., Jesperson, D.C., 1989. The Design and Application of Upwind Schemes on Unstructured Meshes. AIAA Paper 89-0366.

3. Preparation of the Thermal Hydraulic Benchmark V1000CT-2.OECD/DOE/CEA. VVER-1000 Coolant Transient Benchmark Second Workshop;Bieder,2004

4. Investigation of the loop flow mixing in the reactor vessel of Kalinin Unit 1. Kalinin NPP.

5. Kolev, N., Aniel, S., Royer, E., Bieder, U., Popov, D., Topalov, T., 2004. Specifications of the VVER-1000 Vessel Mixing Problems, Commissariat a l’Energie Atomique and OECD Nuclear Energy Agency, VVER-1000 Coolant Transient Benchmark (V1000CT), vol. 2.

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