• Nuclear Engineering and Technology
• /
• v.13 no.1
• /
• pp.1-11
• /
• 1981

The KINS (KAERI-Improved Nodal Simulation) program, a three-dimensional nodal simulation code for pressurized water reactors, has been developed and benchmarked against the first cycle of the Kori-1 reactor. The KINS program is based on the computational model used in FLARE code and has been modified to represent the PWR characteristics more explicitly. The critical boron concentration and three-dimensional power distribution at the beginning of life hot zero power have been calculated and compared with the operating data. A three-dimensional depletion calculation at the intervals of 1000 MWD/MTU turnup steps has been performed. As the result of comparison, our calculation is shown to be in excellent agreement with the operating data. It is displayed that, incorporated with the computing time, the KINS program is an effective and powerful tool for PWR core management.

• Nuclear Engineering and Technology
• /
• v.25 no.2
• /
• pp.248-254
• /
• 1993

The purpose of this study is to evaluate the thermal safety for dry transport of a shipping cask. Analysis condition was based on an ambient temperature of 38$^{\circ}C$ for normal heat condition. The cask was designed to carry 4PWR spent fuel assemblies with a burnup of 38,000 MWD/MTU and 3 years of cooling time. Thermal analysis was carried out by using the COBRA-SFS code. The fuel cavity was considered to be filled with air, nitrogen or helium gas for dry transport. The results of analysis showed that the maximum temperatures of fuel rod cladding in air and helium cavity would be 277$^{\circ}C$ and 226$^{\circ}C$, respectively, for 3 years of cooling time. These values were less than the specified temperature to maintain the thermal integrity of fuel assembly for dry transport.

• Economic and Environmental Geology
• /
• v.28 no.3
• /
• pp.279-286
• /
• 1995

The amount of the high level radioactive wastes in Korea will be increased up to 14,297 MTU about 2010 year. Most of countries adopt the concept of deep burial repository in high level radioactive waste disposal. Because the high level radioactive wastes are very toxic in biosphere and to human, the data verifing its never return to the biosphere are requisite for the disposal. Presently, the evaluating techniques for the high level radioactive waste disposal are not fully developed. Therefore, in order to dispose the high level radioactive wastes in proper time the R & D of it is urged in our country. The R & D and/or the international joint research programme for the disposal of high level wastes have already been proceeded. In our country no plan for its disposal has been prepared. It is the time that the direction of the R & D is to be discused seriously. The R & D for the disposal of high level radioactive wastes in Korea is believed to be focused on developing the pecular techniques such as in situ characteristics of groundwater flowage, and change of properties of in situ rock mass at thermal effects.

• Transactions of the Korean Society of Automotive Engineers
• /
• v.10 no.5
• /
• pp.65-72
• /
• 2002

The closed cycle diesel system is operated in closed circuit system where there is non air breathing with working fluid consists of combination of oxygen, argon and recycled exhaust gas far obtaining underwater or underground power sources. Experimental apparatus using the MTU8V183SE92 high pressurized engine adapted for closed cycle running, capable of operating at the system pressure of maximum 5 bar is constructed with ACAP as data acquisition system in order to operate equally in the open cycle in surface or the closed cycle in submerged conditions. The general features and the characteristics of combustion of HP(high pressure) diesel engine, specially designed and manufactured only for CCDE, are investigated. The test results of performance of HP diesel engine in closed cycle system are presented with respect to power and boost pressure and compared with those of low pressure diesel engine. The oxygen concentration and specific heat ratio are investigated with its deviation

• Proceedings of the Korean Nuclear Society Conference
• /
• 1996.05c
• /
• pp.98-104
• /
• 1996

핵분열 생성물 방출량을 계산하는 모델들에 대한 비교 분석을 위해 GAPCON-THERMAL-2 Revision 2 (GT2R2) 코드를 이용하여 Beyer-Hann , Beyer-Hann with NRC High Burnup Correction, ANS5.4와 Modified ANS5.4 핵분열 생성물 방출 모델들을, RISO-M2-2C 핵연료봉의 실험결과와 비교하였다. Beyer-Hann 모델은 실험결과보다 낮게 예측한반면 ANS5.4 모델은 실험결과 보다 높게 예측하였다. 한편 NRC High Burnup Correction을 한 Beyer-Hann 모텔과Modified ANS5.4 모델은 실험 결과와 비슷한 방출비를 예측하였다. 이러한 결과를 확인하기 위해 국부적인 핵연료 온도와 연소도를 검토한 결과 ANS5.4 모델이 .Modified ANS5.4 모델보다 온도와 연소도에 따라 더 민감한 반응을 보이고 있으며, Beyer-Hann 모텔은 연소도 영향이 없이 각 온도 영역에서 일정하였고, Beyer-Hann with NRC High Burnup Correction 모델은 20,000MWd/MTU 연소도 이상영역에서 연소도 영향을 보이고 있다.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1996.05c
• /
• pp.139-144
• /
• 1996

핵분열 생성물 방출량을 계산하는 모델들에 대한 비교 분석을 위해 GAPCON-THERMAL-2 Revision 2 (GT2R2) 코드를 이용하여 Beyer-Hann , Beyer-Hann with NRC High Burnup Correction, ANS5.4와 Modified ANS5.4 핵분열 생성물 방출 모델들을, RISO-M2-2C 핵연료봉의 실험결과와 비교하였다. Beyer-Hann 모델은 실험결과보다 낮게 예측한반면 ANS5.4 모델은 실험결과 보다 높게 예측하였다. 한편 NRC High Burnup Correction을 한 Beyer-Hann 모델과 Modified ANS5.4 모델은 실험 결과와 비슷한 방출비를 예측하였다. 이러한 결과를 확인하기 위해 국부적인 핵연료 온도와 연소도를 검토한 결과 ANS5.4 모델이 Modified ANS5.4 모델보다 온도와 연소도에 따라 더 민감한 반응을 보이고 있으며, Beyer-Hann 모델은 연소도 영향이 없이 각 온도 영역에서 일정하였고, Beyer-Hann with NRC High Burnup Correction 모델은 20,000MWd/MTU 연소도 이상영역에서 연소도 영향을 보이고 있다.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1996.05c
• /
• pp.553-558
• /
• 1996

가압 경수로형 핵연료에 대한 장기 저장거동을 연구하기 위하여 모의 사용후핵연료(SIMFUEL) 및 조사 핵연료에 대한 산화시험을 공기중에 수행하였다. 연소도가 15,33 및 50 GWD/MTU로 모의한 핵연료를 300-375$^{\circ}C$ 구간에서 산화 시험한 결과, 모의 사용후핵연료는 미조사 $UO_2$시편과 같이 S-형 곡선의 무게증가 특성을 보여 주었으며, 미조사 $UO_2$시편에 비해 산화가 느리게 일어났으며, 모의 사용후핵연료는 연소도가 높을수록 산화속도가 느리다. 고리 2호기에서 2주기 연소한 우라늄 및 가돌리니아 핵연료를 275$^{\circ}C$에서 산화 시험한 결과, 조사 $UO_2$는 연소도가 증가할수록 산화가 느리게 일어나며, 우라늄 핵연료는 가돌리니아 핵연료에 비해 산화가 빨리 일어난다.

• Proceedings of the Korea Information Processing Society Conference
• /
• 2000.10a
• /
• pp.665-668
• /
• 2000

초고속 인터넷의 멀티미디어 서비스 통합에 대한 해결책으로 ATM 네트워크 기술이 널리 사용되고 있다. ATM 서비스를 기반으로 하는 인터넷 프로토콜에서는 ATM 층에서 하나의 셀 손실은 전체 패킷 손실을 초래하여 TCP의 성능이 저하된다. 따라서 혼잡 시 패킷의 손실을 줄이기 위해 UBR 서비스에서는 EPD 방식이, ABR 서비스에서는 ER 방식이 제안되었다. 본 논문에서는, UBR과 ABR 스위치 방식에 빠른 재전송과 회복(FRR)과 Nagle 알고리즘의 사용이 성능향상에 미치는 영향을 TCP 파라미터인 MTU 크기와 LAN 또는 WAN 환경에서 시뮬레이션 평가하였다.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1995.05a
• /
• pp.847-852
• /
• 1995

A shielding analysis for KSC-7, the shipping cask for transporting the 7 PWR spent fuel assemblies, has been carried out. Radiation source term has been calculated on spent fuel with burnup of 50,000 MWD/MTU and 1.5 years cooling time by ORIGEN2 code. The shielding calculation for the cask has been made by using MCNP4A code with continuous cross section data library from ENDF/B-V. As a result of neutron dose rate analysis, another shielding calculational model on spent fuel shipping cask was provided which is using the Monte Carlo method.

• Journal of the Korea Society of Computer and Information
• /
• v.24 no.8
• /
• pp.137-142
• /
• 2019

This paper proposed bitmap based spatial data transmission scheme in need of rapid transmission through network in mobile environment that use and creation of data are frequently happen. Former researches that used clustering algorithms, focused on providing service using spatial data can cause delay since it doesn't consider the transmission speed. This paper guaranteed rapid service for user by convert spatial data to bit, leads to more transmission of bit of MTU, the maximum transmission unit. In the experiment, we compared arithmetically default data composed of 16 byte and spatial data converted to bitmap and for simulation, we created virtual data and compared its network transmission speed and conversion time. Virtual data created as standard normal distribution and skewed distribution to compare difference of reading time. The experiment showed that converted bitmap and network transmission are 2.5 and 8 times faster for each.