Verification of NUREC Code Transient Calculation Capability Using OECD NEA/US NRC PWR MOX/UO2 Core Transient Benchmark Problem
Description
In this report, we verified the NUREC code transient calculation capability using OECD NEA/US NRC PWR MOX/UO2 Core Transient Benchmark Problem. The benchmark problem consists of Part 1, a 2-D problem with given T/H conditions, Part 2, a 3-D problem at HFP condition, Part 3, a 3-D problem at HZP condition, and Part 4, a transient state initiated by a control rod ejection at HZP condition in Part 3. In Part 1, the results of NUREC code agreed well with the reference solution obtained from DeCART calculation except for the pin power distributions at the rodded assemblies. In Part 2, the results of NUREC code agreed well with the reference DeCART solutions. In Part 3, some results of NUREC code such as critical boron concentration and core averaged delayed neutron fraction agreed well with the reference PARCS 2G solutions. But the error of the assembly power at the core center was quite large. The pin power errors of NUREC code at the rodded assemblies was much smaller the those of PARCS code. The axial power distribution also agreed well with the reference solution. In Part 4, the results of NUREC code agreed well with those of PARCS 2G code which was taken as the reference solution. From the above results we can conclude that the results of NUREC code for steady states and transient states of the MOX loaded LWR core agree well with those of the other codes
Availability note (English)
Available from INIS in electronic form; Also available from Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)Files
37122354.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 87 p.
- Report number
- KAERI/TR--3131/2006
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 37122354
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BENCHMARKS; COMPUTER CALCULATIONS; CONTROL ELEMENTS; MIXED OXIDE FUELS; N CODES; PWR TYPE REACTORS; ROD EJECTION ACCIDENTS; TRANSIENTS; VERIFICATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MATERIALS; NUCLEAR FUELS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SOLID FUELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs, 46 figs, 21 tabs