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NEA-1881 ZZ-OSKARSHAMN2

ZZ OSKARSHAMN 2, Oskarshamn-2 (O2) BWR Stability Benchmark

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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-OSKARSHAMN2
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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-OSKARSHAMN2-PROCS NEA-1881/01 Arrived 13-JAN-2014
ZZ-OSKARSHAMN2-DATA NEA-1881/03 Arrived 05-MAR-2014

Machines used:

Package ID Orig. computer Test computer
NEA-1881/01 Many Computers PC Windows
NEA-1881/03 Many Computers PC Windows
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3. DESCRIPTION OF PROGRAM OR FUNCTION


Restricted to the benchmark participants.

Oskarshamn-2 Nuclear Power Plant (Sweden, 1800 MW external loop BWR) experienced stability event on February 25, 1999. A loss of feed-water pre-heaters and control system logic failure resulted in a condition with a high feed-water flow and low feed-water temperature without reactor scram. In addition to the initiating event, an interaction of the automatic power and flow control system caused the plant to move into low flow ? high power regime. Combination of above events culminated in diverging power oscillations which triggered automatic scram at high power.

The benchmark is based on the February 25, 1999 feed-water transient event.  In addition, to increase the confidence on the codes? and models? performance, 5 linear stability measurements before the event and 5 linear stability measurements after the event are included in the benchmark. This benchmark defines a coupled code problem for further validation of thermal-hydraulics system codes for application to BWR stability based on actual plant data from the Oskarshamn-2 Nuclear Power Plant.

Exercises
Phase 1: 1999 Event Analysis ? model the Oskarshamn-2 feed-water transient which occurred on February 25, 1999
-Exercise 1.1: Plant system model initialization
-Exercise 1.2: 3D core model initialization
-Exercise 1.3: Coupled plant system/3-D core simulation
-Exercise 1.4: Sub-channel T/H evaluations (optional)
Phase 2: Analysis of Extreme Scenarios ? challenge codes to the limits of their capabilities
-Exercise 2.1: Limit cycle for global instability
-Exercise 2.2: Limit cycle for regional instability
Phase 3: Blind Model Validation ? BWR stability measurements, uncertainty analysis
-Exercise 3.1: Stability test decay ratio evaluation
-Exercise 3.2: Uncertainty analysis
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9. STATUS
Package ID Status date Status
NEA-1881/01 13-JAN-2014 Masterfiled restricted
NEA-1881/03 05-MAR-2014 Arrived restricted
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. NAME AND ESTABLISHMENT OF AUTHORS

Tomasz KOZLOWSKI
Department of Nuclear, Plasma & Radiological Eng
University of Illinois
216 Talbot Laboratory, MC-234
104 South Wright Street
Urbana, IL 61801
UNITED STATES OF AMERICA

Kostadin IVANOV
Graduate Coordinator, Nuclear Engineering Program
The Pennsylvania State University
206 Reber Bldg
University Park, PA 16802
UNITED STATES OF AMERICA

Tomas LEFVERT
AlbaNova University Center
Royal Institute of Technology
Division of Nuclear Power Safety
SE - 106 91 Stockholm
SWEEDEN
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16. MATERIAL AVAILABLE
NEA-1881/01
- Benchmark documents
Presentations and meeting documents from the 1st Workshop (7-8, May 2012,
hosted by KIT, Karlsruhe, Germany)
Presentations and meeting documents from the 2nd Workshop (April 8-9, 2013,
INSTN-CEA/Saclay)

NEA-1881/03
- Benchmark documents
Conditions for release (Non-disclosure agreement form)
- Benchmark data (Benchmark package 2014-02)
Reference data boundary conditions
Reference data calculated
Reference data cross sections (available in CASMO and PMAXS formats, exposure
and history)
Reference data measured
Reference data specifications
- Benchmark Results
To be added
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: benchmarks, boiling water reactor, linear stability, thermal-hydraulics system codes, transients.