Coupling of Time-Dependent Neutron Transport Theory with the Thermal Hydraulics Code ATHLET and Application to the Research Reactor FRM-II-Reference-Cited by-同舟云学术

Coupling of Time-Dependent Neutron Transport Theory with the Thermal Hydraulics Code ATHLET and Application to the Research Reactor FRM-II

Published:2003-11 Issue:3 Volume:145 Page:320-341
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Pautz Andreas¹,Birkhofer Adolf²

Affiliation:

1. Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH Forschungsgelände, 85748 Garching, Germany

2. Technische Universität München Lehrstuhl für Reaktordynamik und Reaktorsicherheit Forschungsgelände, 85748 Garching, Germany

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE03-A2386

Reference22 articles.

1. RELAP DEVELOPMENT TEAM, “RELAP5/MOD3.2 Code Manual,” NUREG/CR-5535, INEL-95/0174, Idaho National Engineering Laboratory (1995).

2. Coarse-Mesh Flux-Expansion Method for the Analysis of Space-Time Effects in Large Light Water Reactor Cores

3. A. S. DiGIOVINE et al. “SIMULATE-3: Advanced Three Dimensional Two-Group Reactor Analysis Code, User’s Manual,” STUDSVIK/SOA-95/15, Studsvik (1995).

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