NUREG/CR-7164, Cross Section Generation Guidelines for TRACE-PARCS
نویسندگان
چکیده
................................................................................................................................. iii TABLE OF CONTENTS ................................................................................................................ v LIST OF FIGURES ..................................................................................................................... vii LIST OF TABLES ......................................................................................................................... ix ACRONYMS AND ABBREVIATIONS .......................................................................................... xi 1.0 INTRODUCTION ................................................................................................................... 1 2.0 FUEL SPECIFICATIONS FOR THIS STUDY ........................................................................ 3 2.1. SPECIFICATIONS OF PEACH BOTTOM TYPE 3C FUEL ............................................ 3 2.2. SPECIFICATIONS OF PMAXS STRUCTURE ............................................................... 4 2.3. SPECIFICATIONS OF LATTICE CODES ...................................................................... 4 3.0 COMPARISONS OF CROSS SECTION SETS ..................................................................... 7 3.1. COMPARISONS OF CROSS SECTIONS...................................................................... 7 3.2. BENCHMARK BETWEEN TRITON AND KENO .......................................................... 11 3.3. COMPARISONS OF KINETICS PARAMETERS ......................................................... 11 3.3.1. 1/v .......................................................................................................................... 11 3.3.2. βeff .......................................................................................................................... 12 4.0 SENSITIVITY ANALYSIS OF CROSS SECTIONS ............................................................. 17 4.1. DC HISTORY EFFECTS .............................................................................................. 17 4.1.1. Results of Single CHAN Model ............................................................................. 21 4.1.2. Results of Oskarshamn Core-wide Stability .......................................................... 22 4.1.3. Results of Ringhals Core-wide Stability ................................................................ 23 4.1.4. Conclusion of DC History Effects .......................................................................... 24 4.2. DC BRANCH EFFECTS ............................................................................................... 24 4.2.1. Results for Single CHAN Model ............................................................................ 25 4.2.2. Results for Oskarshamn Core-wide Stability ......................................................... 27 4.2.3. Results for Ringhals Core-wide Stability ............................................................... 28 4.2.4. 4.2.4 Conclusions of DC Branch Effects ............................................................... 29 5.0 EFFECTIVE DELAYED NEUTRON FRACTION ................................................................. 31 5.1. DEFINITION OF βeff ...................................................................................................... 31 5.2. CALCULATION OF βeff USING A SINGLE-ASSEMBLY LATTICE .............................. 31 5.3. PHYSICAL DESCRIPTION OF THE PHENOMENA .................................................... 32 5.4. NUMERICAL SIMULATION ......................................................................................... 35 6.0 CODE-TO-CODE COMPARISON ....................................................................................... 39
منابع مشابه
The Analysis of TRACE/PARCS in the Simulation of Ultimate Response Guideline for Lungmen ABWR
In this research, the TRACE/PARCS model of Lungmen ABWR has been developed for verification of ultimate response guideline (URG) efficiency. This ultimate measure was named as DIVing plan, abbreviated from system depressurization, water injection and containment venting. The simulation initial condition is 100% rated power/100% rated core flow. This research focuses on the estimation of the tim...
متن کاملTRACE/PARCS Calculations of Exercises 1 and 2 of the V1000CT-2 Benchmark
Exercises 1 and 2 of the VVER-1000 Coolant Transient Benchmark Phase 2 (V1000CT-2) are investigated using coupled three-dimensional (3-D) neutron kinetics/thermal-hydraulics code TRACE/PARCS. Two coarse mesh 3-D thermal-hydraulic models (with six angular sectors and with eighteen angular sectors) were developed for the system code TRACE for Exercise 1 and their applicability is evaluated using ...
متن کاملNUREG/CR-6119 Vol 2 Rev 2 [3:3] "MELCOR Computer Code Manuals: Reference Manuals Version 1.8.5" S102520-03X
متن کامل
NUREG/IA-0215 "Spatial Effects and Uncertainty Analysis for Rod Ejection Accidents in a PWR."
DISCLAIMER: This report was prepared under an international cooperative agreement for the exchange of technical information. Neither the U.S. Government nor any agency thereof, nor any employee, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, of any information, apparatus, product or process disclo...
متن کامل