Search | Korea Science

CHUNG HEE M.
- Nuclear Engineering and Technology
- /
- v.37 no.4
- /
- pp.327-362
- /
- 2005
The design, construction, and operation of a light water reactor (LWR) are subject to compliance with safety criteria specified for accident situations, such as loss-of-coolant accident (LOCA) and reactivity-initiated accident (RIA). Because reactor fuel is the primary source of radioactivity and heat generation, such a criterion is established on the basis of the characteristics and performance of fuel under the specific accident condition. As such, fuel behavior under accident situations impact many aspects of fuel design and power generation, and in an indirect manner, even spent fuel storage and management. This paper provides a comprehensive review of: the history of the current LOCA criteria, results of LOCA-related investigations on conventional and new classes of fuel, and status of on-going studies on high-burnup fuel under LOCA situations. The objective of the paper is to provide a better understanding of important issues and an insight helpful to establish new LOCA criteria for modem LWR fuels.
PDF KSCI

Baek, Byung-Chan;Lee, Chang-Kue;Lee, Chung-Chan;Zee, Sung-Quun
- Proceedings of the Korean Nuclear Society Conference
- /
- 1996.05a
- /
- pp.538-544
- /
- 1996
This paper presents the results of the core follow analysis for Yonggwang Unit 3 Cycle 1. The values of peaking factors (Fxy, Fq, Fr anf Fz) and core power distribution measured and processed by CECOR code［1］ are compared with those predicted by ROCS code［2］, The measured boron rundown is also compared with the predicted values. As results, the comparison of peaking factors, radial and axial power distributions and boron rundown between the measured and the predicted show good agreement throughout the cycle. Additionally, assembly burnup differences between CECOR and ROCS at EOC1 (13650 MWD/MTD are within 5% of core average burnup.
PDF

Sorenson, Ken B.;Hanson, Brady
- Nuclear Engineering and Technology
- /
- v.45 no.4
- /
- pp.421-426
- /
- 2013
The need for extended storage of used nuclear fuel is increasing globally as disposition schedules for used fuel are pushed further into the future. This is creating a situation where dry storage of used fuel may need to be extended beyond normal regulatory licensing periods. While it is generally accepted that used fuel in dry storage will remain in a safe condition, there is little data that demonstrate used fuel performance in dry storage environments for long periods of time. This is especially true for high burnup used fuel. This paper discusses a technical approach that defines a process that develops the technical basis for demonstrating the safety of used fuel over extended periods of time.
https://doi.org/10.5516/NET.06.2013.707 인용 PDF KSCI KPUBS

Ta, Duy Long;Hong, Ser Gi;Lee, Deokjung
- Nuclear Engineering and Technology
- /
- v.53 no.1
- /
- pp.19-29
- /
- 2021
This paper presents the validation of the MCS code for critical safety analysis with burnup credit for the spent fuel casks. The validation process in this work considers five critical benchmark problem sets, which consist of total 80 critical experiments having MOX fuels from the International Criticality Safety Benchmark Evaluation Project (ICSBEP). The similarity analysis with the use of sensitivity and uncertainty tool TSUNAMI in SCALE was used to determine the applicable benchmark experiments corresponding to each spent fuel cask model and then the Upper Safety Limits (USLs) except for the isotopic validation were evaluated following the guidance from NUREG/CR-6698. The validation process in this work was also performed with the MCNP6 for comparison with the results using MCS calculations. The results of this work showed the consistence between MCS and MCNP6 for the MOX fueled criticality benchmarks, thus proving the reliability of the MCS calculations.
https://doi.org/10.1016/j.net.2020.06.016 인용 PDF KSCI