last modified: 10-DEC-2003 | catalog | categories | new | search |

NEA-1554 ZZ-PWR-MSLB.

ZZ PWR-MSLB, PWR Main Steam-Line Break Benchmarks, Coupled Neutronics Thermal-Hydraulics

top ]
1. NAME OR DESIGNATION OF PROGRAM:  ZZ-PWR-MSLB.
top ]
2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
ZZ-PWR-MSLB-REV.4 NEA-1554/05 Tested 10-DEC-2003

Machines used:

Package ID Orig. computer Test computer
NEA-1554/05 Many Computers PC bi-Pentium III 1GHz
top ]
3. DESCRIPTION OF PROGRAM OR FUNCTION

- PWR-MSLB is a Main Steam-Line Break (MSLB) benchmark problem derived from the reactor geometry and operational data of the Three Mile Island Unit 1 (TMI-I) nuclear power plant. The objective of the benchmark is to verify the capability of coupled neutronics - thermal-hydraulics code systems to analyse complex transients with coupled core-plant interaction, and to fully test the thermal-hydraulic coupling. A three dimensional neutronics core model has been defined. The benchmark consists of three exercises:
1. Point kinetics plant simulation
2. Coupled neutronics/core thermal-hydraulics evaluation of core    response from a multi-dimensional (3-D) perspective
3. Best-estimate coupled core - plant transient modeling
This package contains the text of the four reports produced, the first one of which contains the specification, tables, pictures and numerical data  files required for the modeling of the MSLB event.
top ]
4. METHOD OF SOLUTION:
top ]
5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
top ]
6. TYPICAL RUNNING TIME
top ]
7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM
top ]
8. RELATED OR AUXILIARY PROGRAMS: RELATED AND AUXILIARY PROGRAMS
top ]
9. STATUS
Package ID Status date Status
NEA-1554/05 10-DEC-2003 Screened
top ]
10. REFERENCES
NEA-1554/05, included references:
- K.N. Ivanov et al.:
Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark
Volume I: Final Specifications
NEA/NSC/DOC(99)8 (April 1999)
- T. Beam et al.:
Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark
Volume II: Summary Results of Phase I (Point Kinetics)
NEA/NSC/DOC(2000)21 (December 2000)
- N. Todorova, B. Taylor, and K. Ivanov:
Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark
Volume III: Results of Phase II on 3-D Core Boundary Conditions Model
NEA/NSC/DOC(2002)12
- N. Todorova, K. Ivanov, and  B. Taylor:
Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark
Volume IV: Results of Phase III on Coupled Core-plant Transient Modelling
NEA/NSC/DOC(2003)21, ISBN 92-64-02152-3
top ]
11. HARDWARE REQUIREMENTS: MACHINE REQUIREMENTS
top ]
12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
top ]
13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  Unix or non-Unix  systems.
top ]
14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

Document requires either Word or WordPerfect processors.
top ]
15. NAME AND ESTABLISHMENT OF AUTHORS

    K. N. Ivanov, T. M. Beam, and Anthony J. Baratta
    Department of Nuclear Engineering
    The Pennsylvania State University
    University Park, PA 16802, USA

    A. Irani and N. Trikouros
    GPU Nuclear Inc.
    One Upper Pond Road
    Parsipanny, NJ 07054, USA
top ]
16. MATERIAL AVAILABLE
NEA-1554/05
non-Unix\mslbdata    data for the specification of MSLB (non-Unix):
3D-BC      Core T/H Boundary Conditions Model
NoRP   no return to power
RP     return to power
Decay-Heat  decay-heat data
Results    position of Control Rod Groups
XS-Lib     cross-section libraries for the 3D kinetics
mslbspec      final specification - Word format
Unix\mslbdata    data for the specification of MSLB (Unix):
3D-BC     Core T/H Boundary Conditions Model
NoRP   no return to power
RP     return to power
Decay-Heat decay-heat data
Results    position of Control Rod Groups
XS-Lib     cross-section libraries for the 3D kinetics
mslbspec       final specification - PDF format
nsc-doc99-8.pdf Volume 1: Final Specifications
nsc-doc2000-21.pdf  Volume 2: Summary Results of Phase I (Point Kinetics)
nsc-doc2002-12.pdf  Vol 3:Results of Phase II on 3-D Core Boundary Conditions Model
Volume 4: Results of Phase III on Coupled Core-plant Transient Modelling
top ]
17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: pwr reactors, reactor cores, transients.