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NEA-1780 PWR-MOX/UOX-TRANS.

PWR-MOX/UOX-TRANS, OECD/NEA US-NRC PWR MOX/UO2 Core Transient Benchmark

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1. NAME OR DESIGNATION:  PWR-MOX/UOX-TRANS.
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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
PWR-MOX/UOX-TRANS NEA-1780/01 Arrived 16-FEB-2007

Machines used:

Package ID Orig. computer Test computer
NEA-1780/01 Many Computers
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3. DESCRIPTION OF BENCHMARK

The present benchmark is designed to provide the framework to assess the ability of modern reactor kinetic codes to predict the transient response of a core partially loaded with MOX fuel.  This benchmark employs many of the characteristics of the NEACRP L-335 PWR benchmark proposed by Finnemann in 1991 which was designed to assess the ability of spatial kinetics codes to model rod ejection transients.  The current problem adds the complexity of modelling a rod eject in a core fuelled partially with weapons grade MOX.  The core chosen for the simulation is based on four-loop Westinghouse PWR power plant similar to the reactor chosen for Plutonium disposition in the U.S.
  
The problem is designed primarily to assess core simulators, and therefore few group constants are specified at the level of homogenized pin cells.  However, some participants may wish to utilize their own cross section generation methodology or to model explicitly the heterogeneous pins in their core simulators.  Therefore, the benchmark also specifies material compositions and pin geometries in order to reach the widest range of participants and in order to be applicable to continuing code developments in which heterogeneous full core transport transients are becoming possible.
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9. STATUS
Package ID Status date Status
NEA-1780/01 16-FEB-2007 Masterfiled restricted
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10. REFERENCES
NEA-1780/01, included references:
- Tomasz Kozlowski (Purdue University and KTH, Sweden), Thomas J. Downar
(Purdue University):
PWR MOX/UO2 Core Transient Benchmark - Final Report), ISBN 92-64-02330-5,
NEA/NSC/DOC(2006)20, December 2006
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12. PROGRAMMING LANGUAGE(S) USED

No item found

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15. NAME AND ESTABLISHMENT OF AUTHORS

Tomasz KOZLOWSKI
KTH Nuclear Power Safety
KTH (Royal Institute of Technology)
Roslagstullsbacken 21
10691 Stockholm, Sweden
  
Thomas J. DOWNAR
School of Nuclear Engineering
Purdue University
1290 Nuclear Engineering Bldg
W. LAFAYETTE, IN 47907-1290, USA
  
This information is restricted to benchmark participants.
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16. MATERIAL AVAILABLE
NEA-1780/01
- Benchmark documents
PWR MOX/UO2 Core Transient Benchmark - Final Report (January 2007)
Final Powerpoint presentation to the WPRS (January 2006)
Answers to questions (last update:  May 30, 2006)
Specifications (last update:  December 1, 2003)
Submittal templates (last update:  December 1, 2003)
- Benchmark data
Material number densities (last update:  December 1, 2003)
2G nodal cross section library (last update:  July 9, 2004)
4G nodal cross section library (last update:  July 9, 2004)
4G nodal cross section library without upscattering (last upd.:9 Jul.04)
8G nodal cross section library (last update:  July 9, 2004)
8G cell cross section library (last update:  July 9, 2004)
1G pin-power form functions (last update:  May 10, 2004)
2G pin-power form functions (last update:  May 10, 2004)
4G pin-power form functions (last update:  May 10, 2004)
- Benchmark Results
heterogeneous:
BARS 5G heterogeneous transport solution, Kurchatov Inst. Russia (upd.1
Feb. 06)
DeCART 47G heterogeneous transport solution, Seoul Nat. Univ. and KAERI, Korea
(upd. 1 Feb.06)
DORT 16G heterogeneous transport solution, GRS, Germany (last update: 1 Feb. 06)

MCNP continuous energy heterogeneous transport solution, Kurchatov Inst. Russia
(upd. 1 Feb.06)
Nodal:
CORETRAN 2G 1/FA nodal diffusion solution, PSI, Switz. (last update: 1 Feb.06)
CORETRAN 2G 4/FA nodal diffusion solution, PSI, Switz. (last update: 1 Feb.06)
NUREC 2G nodal diffusion solution, KAERI, Korea (last update: 1 Feb.06)
PARCS 2G nodal diffusion solution, Purdue Univ. USA (last update: 1 Feb.06)
PARCS 4G nodal diffusion solution, Purdue Univ. USA (last update: 1 Feb.06)
PARCS 8G nodal diffusion solution, Purdue Univ. USA (last update: 1 Feb.06)
SKETCH-INS 2G nodal diffusion solution, JNES, Japan (last update:1 Feb. 06)
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: MOX, core, pressurized water reactor, rod ejection, transients.