COUPLED THERMAL-HYDRAULIC/ NEUTRONICS/CRUD FRAMEWORK IN PREDICTION OF CRUD-INDUCED POWER SHIFT PHENOMENON.
- Published in:
- Nuclear Technology, 2013, v. 183, n. 3, p. 535, doi. 10.13182/NT13-A19440
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- Article
Works matching IS 0029-5450 AND VI 183 AND IP 3 AND DT 2013
Results: 25
1
2
DEVELOPMENT OF A THREE-DIMENSIONAL PSEUDO PIN-BY-PIN CALCULATION METHODOLOGY IN ANC.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 527, doi. 10.13182/NT13-A19439
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- Article
3
A STATISTICAL SAMPLING METHOD FOR UNCERTAINTY ANALYSIS WITH SCALE AND XSUSA.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 515, doi. 10.13182/NT12-112
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- Article
4
VALIDATION OF THE U.S. NRC COUPLED CODE SYSTEM TRITON/TRACE/PARCS USING THE SPECIAL POWER EXCURSION REACTOR TEST III.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 504, doi. 10.13182/NT13-A19437
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- Article
5
COUPLED 3-D NEUTRONICS/THERMAL-HYDRAULICS OPTIMIZATION STUDY FOR IMPROVING THE RESPONSE OF A 3600 MW(THERMAL) SFR CORE TO AN UNPROTECTED LOSS-OF-FLOW ACCIDENT.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 484, doi. 10.13182/NT13-A19436
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- Article
6
REACTIVITY IMPACT OF <sup>16O</sup> THERM ELASTIC-SCATTERING NUCLEAR DATA FOR SOME NUMERICAL AND CRITICAL BENCHMARK SYSTEMS.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 473, doi. 10.13182/NT13-A19435
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7
EFFECTS OF NUCLEAR DATA UNCERTAINTIES ON THE NEA/OECD PWR MOX/UO<sub>2</sub> CORE ROD EJECTION BENCHMARK.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 464, doi. 10.13182/NT183-464
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- Article
8
STRAIN-RATE SENSITIVITY ANALYSIS FOR Ni ALLOYS TO BE USED IN VERY HIGH TEMPERATURE REACTORS.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 455, doi. 10.13182/NT13-A19433
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- Article
9
FEATURES OF HYBRID CORE CALCULATIONS AT BFS-62-3A EXPERIMENTS.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 446, doi. 10.13182/NT13-A19432
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- Article
10
PRESSURIZED WATER REACTOR ENDF/B-VII CROSS-SECTION LIBRARIES FOR ORIGEN-ARP.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 436, doi. 10.13182/NT13-A19431
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- Article
11
DESIGN OF ULTRALONG-CYCLE FAST REACTOR EMPLOYING BREED-AND-BURN STRATEGY.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 427, doi. 10.13182/NT13-A19430
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- Article
12
APPLICATION OF RADIOGENIC LEAD WITH DOMINANT CONTENT OF <sup>208</sup>Pb FOR LONG PROMPT NEUTRON LIFETIME IN FAST REACTOR.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 409, doi. 10.13182/NT13-A19429
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- Article
13
WIMS/PANTHER ANALYSIS OF UO<sub>2</sub>/MOX CORES USING EMBEDDED SUPERCELLS.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 398, doi. 10.13182/NT13-A19428
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- Article
14
VERIFICATION OF A DEPLETION METHOD IN SCALE FOR THE ADVANCED HIGH-TEMPERATURE REACTOR.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 391, doi. 10.13182/NT13-A19427
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- Article
15
SCALE CODE VALIDATION FOR PRISMATIC HIGH-TEMPERATURE GAS-COOLED REACTORS.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 379, doi. 10.13182/NT13-A19426
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- Article
16
REACTIVITY EFFECTS OF SPATIAL HOMOGENIZATION OF THERMAL FEEDBACK REGIONS IN MONTE CARLO REACTOR CALCULATIONS.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 367, doi. 10.13182/NT13-A19425
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- Article
17
SIMULATION OF IN-CORE NEUTRON NOISE MEASUREMENTS FOR AXIAL VOID PROFILE RECONSTRUCTION IN BOILING WATER REACTORS.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 354, doi. 10.13182/NT13-A19424
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- Article
18
TRANSITION TO CASMO-5M AND SIMULATE-3K FOR STABILITY ANALYSES OF THE SWISS BOILING WATER REACTORS.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 341, doi. 10.13182/NT13-A19423
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19
NEUTRONICS AND DEPLETION METHODS FOR MULTIBATCH FLUORIDE SALT-COOLED HIGH-TEMPERATURE REACTORS WITH SLAB FUEL GEOMETRY.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 331, doi. 10.13182/NT13-A19422
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- Article
20
ANALYSIS OF PIN REMOVAL EXPERIMENTS CONDUCTED IN A SUPERCRITICAL LIGHT WATER REACTOR-LIKE TEST LATTICE.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 321, doi. 10.13182/NT13-A19421
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21
CORE DESIGN, SPENT-FUEL CHARACTERISTICS ASSESSMENT, AND FUEL CYCLE ANALYSIS FOR THORIUM-URANIUM BREEDING RECYCLE IN PRESSURIZED WATER REACTORS.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 308, doi. 10.13182/NT13-A19420
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22
DRYOUT METHODOLOGY WITH NEW STEADY-STATE CRITERION AND MORE-ACCURATE STATISTICAL TREATMENT OF CHANNEL BOW.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 298, doi. 10.13182/NT13-A19419
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- Article
23
TRADE-OFF STUDY ON THE POWER CAPACITY OF A PROTOTYPE SODIUM-COOLED FAST REACTOR IN KOREA.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 287, doi. 10.13182/NT13-A19418
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24
MACROSCOPIC AND MICROSCOPIC PACKING PROPERTIES OF EXPERIMENTAL AND COMPUTATIONAL PEBBLE BEDS.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 272, doi. 10.13182/NT13-A19417
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25
FOREWORD.
- Published in:
- Nuclear Technology, 2013, v. 183, n. 3, p. 271, doi. 10.13182/NT13-A19416
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