Published 2001 | Version v1
Book

Development and benchmarking of the DYN3D/RELAP5 code system

  • 1. Institute of Physics and Power Engineering (IPPE), Obninsk (Russian Federation)
  • 2. Forschungszentrum Rossendorf e.V. (FZR), Dresden (Germany)

Description

The integration of advanced computer codes from different safety analysis areas into code systems of expanded modeling capabilities results in a more detailed and accurate representation of reactor plant structural components. Less conservative predictions of advanced codes are needed to represent the transient behavior of advanced fuels (inert-matrix fuels or IMFs) being developed for burning the plutonium in thermal reactors and/or for improving the safety features of LWRs. IPPE is participating in domestic and international research programs on advanced reactor concepts based on new fuel types for LWRs. These programs cover both fuel technology and analytical tool development areas and, as one of their aspects, envisages elaboration of the interface for coupling the US system code RELAP5/MOD3 and the German 3-dimensional neutron kinetics code DYN3D. As a result of the joint FZR-IPPE research project, the coupled code system DYN3D/RELAP5 has been developed. (orig.)

Part of:
Annual meeting on nuclear technology 2001. Proceedings

Additional details

Additional titles

Original title (English)
Jahrestagung Kerntechnik 2001. Tagungsband

Publishing Information

Publisher
Inforum
Imprint Place
Bonn (Germany)
Imprint Title
Annual meeting on nuclear technology 2001. Proceedings
Imprint Pagination
734 p.
Journal Page Range
p. 15-18
ISSN
0720-9207

Conference

Title
2001 annual meeting on nuclear technology
Original Conference Title
Jahrestagung Kerntechnik (JK) 2001
Dates
15-17 May 2001
Place
Dresden (Germany)

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
32052345
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BENCHMARKS; D CODES; KINETICS; NEUTRON TRANSPORT; R CODES; REACTOR PHYSICS; SAFETY ANALYSIS; THERMODYNAMICS; TRANSIENTS
Descriptors DEC
COMPUTER CODES; NEUTRAL-PARTICLE TRANSPORT; PHYSICS; RADIATION TRANSPORT

Optional Information

Notes
4 refs. Imprint:Jahrestagung Kerntechnik 2001. Tagungsband