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NEA-1398 ZZ-3DLWRCT.

ZZ 3DLWRCT, 3-D LWR Rod Ejection and Rod Withdrawal Benchmarks

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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-3DLWRCT.
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2. COMPUTERS
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Program name Package id Status Status date
ZZ-3DLWRCT-1 NEA-1398/02 Tested 27-JUN-1995
ZZ-3DLWRCT-2 NEA-1398/03 Arrived 08-JAN-2002

Machines used:

Package ID Orig. computer Test computer
NEA-1398/02 Many Computers DEC VAX 6000
NEA-1398/03 Many Computers
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3. DESCRIPTION:  3-D LWR Rod Ejection and Rod Withdrawal Benchmarks.
NEA-1398/02
- 3DLWRCT-1 represents the first phase of a series of LWR core transient benchmarks. It consists of 2 parts:

. PWR problem : ejection of a control assembly from an initially critical core at hot zero power or at full power, each for three different geometrical configurations. The set of problems offers a variety of reactivity excursions which efficiently test the coupled neutronic/thermal-hydraulic models of the codes.

. BWR problem: reactivity excursions caused by cold water injection and pressurization events.

2-group macroscopic cross sections and their derivatives respect to boron density, moderator temperature, moderator density and fuel temperature for BWR and PWR core materials are included.
For the PWR cases, 63 submitted solutions are analyzed in comparison with a nodal reference solution defined by using a finer spatial and temporal resolution than in standard calculations, which is included. For the BWR benchmark only the cold water injection event is discussed and evaluated in some detail. Lacking a reference solution, the evaluation of the 8 sets of BWR contributions relies on synthetic comparative discussion. - 3DLWRCT-2 represents the second phase of the PWR core transient benchmark and concerns an uncontrolled withdrawal of control rods at zero power. The same cross section data as for phase I is used.

NEA-1398/03
- 3DLWRCT-2 represents the second phase of the benchmark and concerns the results of the "rod withdrawal from zero power" benchmark, including the solutions obtained by ten participants, from ten different countries, and a reference solution, obtained by refining the spatial and time meshing.
        The problem is mathematically well defined. The specification provides cross-sections for fuel, reflector and absorbers. Four cases are analysed. The submitted solutions are compared to a reference obtained with a nodal code using finer spatial and temporal resolution than in standard calculation. Besides global information such as fission power evolution, the set of results also includes local maxima, as well as hot pellet enthalpy and cladding temperature.
        In general, a good agreement is obtained for most of the codes on the power evolution and its integral, in particular for the core averaged parameters. For the "hot pellet", the spread of the results is more important; however, the assumptions that define and localise this pellet are not the same for each participant: a finer local power profile reconstruction leads to more severe effects. This shows that one must take care of the consistency between the calculation methodology and the criteria applied to the safety analyses.
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4. METHOD OF SOLUTION:
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME:
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
NEA-1398/02 27-JUN-1995 Tested at NEADB
NEA-1398/03 08-JAN-2002 Masterfiled Arrived
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10. REFERENCES:
NEA-1398/02, included references:
- H. Finnemann and A. Galati:
  NEACRP 3-D LWR Core Transient Benchmark
  NEACRP-L-335, Revision 1, (January 1992).
- H. Finnemann:
  Complement to Benchmark Specification NEACRP-L-335
  Letter of (February 18, 1992).
- H. Finnemann, H. Bauer, A. Galati and R. Martinelli:
  Results of LWR Core Transient Benchmarks
  NEA/NSC/DOC(93)25 (October 1993)
NEA-1398/03, included references:
- R. Fraikin et al.:
  NEA-NSC 3-D/1-D PWR Core Transient Benchmark Uncontrolled
  Withdrawal of Control Rods at Zero Power
  Final Specifications
  NEA/NSC/DOC(93)9 Rev. 1 (September 1993)
- R. Fraikin:
  PWR Benchmark on Uncontrolled Rods Withdrawal at Zero Power
  Final Report
  NEA/NSC/DOC(96)20 (September 1997)
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11. MACHINE REQUIREMENTS:
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12. PROGRAMMING LANGUAGE(S) USED

No item found

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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

         A. Galati
         ENEA CRE Casaccia
         CP 2400
         I-00100 Roma A.D., Italy

         H. Finnemann and H. Bauer
         SIEMENS AG - Power Generation Group (KWU)
         D-8520 Erlangen, Germany

         R. Fraikin
         TRACTEBEL ENERGY ENGINEERING
         Brussels, Belgium
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16. MATERIAL AVAILABLE
NEA-1398/03
0_re_a.dat Test case
0_re_b.dat Test case
0_re_c.dat Test case
0_re_d.dat Test case
96-0020.doc Final report (Word document)
96-0020.pdf Final report (PDF format)
R_a.xls Graphs
R_b.xls Graphs
R_c.xls Graphs
R_d.xls Graphs
T_a.xls Graphs
T_b.xls Graphs
T_c.xls Graphs
T_d.xls Graphs
Z_a.xls Graphs
Z_b.xls Graphs
Z_c.xls Graphs
Z_d.xls Graphs
NEA-1398/02
File name File description Records
NEA1398_02.001 This information file 64
NEA1398_02.002 3D LWR Core Transient BWR X-sec and Derivat. 118
NEA1398_02.003 3D LWR Core Transient PWR X-sec and Derivat. 114
NEA1398_02.004 3D PWR Case A1 A2 PANTHER Reference Solution 1619
NEA1398_02.005 3D PWR Case B1 B2 PANTHER Reference Solution 1586
NEA1398_02.006 3D PWR Case C1 C2 PANTHER Reference Solution 1485
NEA1398_02.007 PWR Deviation from Reference - Selection 546
NEA1398_02.008 PWR Evaluation of Axial Power (A1) 1251
NEA1398_02.009 PWR Evaluation of Axial Power (A2) 1013
NEA1398_02.010 PWR Evaluation of Axial Power (B1) 1251
NEA1398_02.011 PWR Evaluation of Axial Power (B2) 1013
NEA1398_02.012 PWR Evaluation of Axial Power (C1) 2829
NEA1398_02.013 PWR Evaluation of Axial Power (C2) 2351
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: BWR reactors, LWR reactors, boron, cross sections, experimental data, moderators, pwr reactors, reactor cores, transients.