이 연구는 핵무기 폭발 시 발생하는 효과 변인을 토대로 북한이 언제, 어떤 방법으로 핵무기를 운용할 것이며, 핵폭발 시 생성되는 방사성 물 질이 자연환경과 인공물의 영향에 따라 도심지에서 어떤 거동 현상을 보 이는가와 이를 고려한 국민 방호의 대비 방향에 관한 것이다. 연구 결과 핵무기는 폭발 고도에 따라 그 효과가 달라지며, 북한은 이를 활용하여 개전 초부터 가장 효과적인 공격을 할 것으로 예측되었다. 즉, 북한은 개 전 초 한미연합군과 정부의 지휘‧통제‧통신체계를 무력화하기 위해 저위 력핵무기로 지하 폭발을, 전쟁 도중 결정적인 목표 확보를 위해 전술핵 무기로 저공 폭발을, 전쟁 말기 패색이 짙어지는 위기 시에는 전술핵무 기로 지표면 폭발을 시도할 것이다. 북한의 핵무기 공격 후 발생되는 방 사성 물질은 낙진의 형태로 일정 지역을 오염시킬 것이며, 방사성 물질 이 도심지로 유입된다면 공기역학 또는 유체역학적 거동을 보임으로써 다양한 형태의 오염과 위험이 존재할 것으로 분석되었다. 이에 따라 국 민 방호를 위해서는 북한의 핵무기 공격 양상을 고려 최악의 상황을 가 정한 대비가 평시에 완료되어야 하며, 전쟁 개시 이후에는 당시의 공격 유형에 부합한 대응 및 복구가 뒤따라야 한다. 아울러 방사능 낙진의 거 동을 세밀히 분석하고 이를 고려하여 핵폭발 초기 효과에 대비하는 주민 대피와 이를 후속하는 낙진에 대응하기 위한 주민 소개는 분리되어야 한다.

An air cleaning unit(ACU) in a nuclear power plant plays a role on cooling the safety-related components whose function is involved in the reactor shutdown, and maintains the suitable temperature and humidity for work in the rooms where an operator is working on. To guarantee the performance of the unit the design of ACU should be subject to credible codes and standards, such as ASME, ANSI and ASHRAE, etc. On top of them, the desorption of the carbon adsorber is addressed in ASME N509 which causes the adsorber no longer to capture the iodine isotopes produced by the severe accident. In this study, the equations of the heat source were derived from the radioactive decay heat of each iodine isotopes. From the resultant equation, the maximum temperature below 300oF for the desorption was calculated under a proposed condition and analysed with the reference results.

In this paper, as the transport cask was moved in the reactor, the structural integrity on the cask had to be evaluated in the normal transport condition. The drop height of the cask was determined by the weight of the cask in the normal transport condition by regulations about assessment test. It was determined that the drop height of the cask was 1.2 m by regulations. The velocity of the drop impact was calculated to perform the drop impact analysis by the principle of the conservation of energy. Using results of the simulation about the drop impact analysis, the structural integrity assessment on the transport cask was performed by ASME Boiler and Pressure Vessel Code.

원자력발전소의 1차 계통에서 오염된 장비들을 취급이 용이하고 안전하게 운반하기 위한 운반용기는 내부의 방사성 물질에 대한 방사능 평가에 의하여 방사성물질 A형 운반용기로 분류된다. 방사성물질 A형 운반용기는 IAEA Safety Standard Series No. ST-1 및 국내 원자력법 등 관련규정의 기술기준을 만족하여야 하는데, 운반용기는 중량에 따라 0.31.2m의 높이에서 소성이 일어나지 않는 단단한 바닥면으로 가장 심각한 손상을 주는 방향으로 낙하시키는 정상운반조건(normal transport conditions)에 대하여 구조적 건전성을 유지하여야 한다. 여기서는 ABAQUS/Explicit 코드를 이용하여 컨테이너형태의 A형 운반용기에 대하여 최대손상이 야기되는 0.9m 경사낙하조건에 대한 3차원 충격해석을 수행하고 구조적 건전성을 평가하였는데, 운반용기는 경사낙하시 코너피팅(corner fitting)의 분쇄(crush)에 의하여 대부분의 충격을 흡수하였으며 운반용기의 격납경계는 구조적 건전성을 유지하였다.

Laws and regulations of radioactive waste management related to the Exemption system and the Clearance systembetween governing authorities in Korea and Japan were investigated to suggest better management of radioactive waste.Above both system, very low levels of radioactive wastes which have negligible risk can be decided on being Exclusionsystem and classified as a non-radioactive waste. As a result, the Exemption systems between two countries were similar,whereas the Clearance systems were different. With regard to laws related to the Clearance, Japan specify providinginformation and feedback among relevant authorities, but there is no specification in Korea. In addition, this study suggeststo develop accredited analysis methods to improve the accuracy and reproducibility of the measurement, because twocountries have not established the national accredited analysis method for determining the concentration of radionuclide.

The characteristics of atmospheric dispersion of radioactive material (i.e. 137Cs) related to local wind patterns around the Kori nuclear power plant (KNPP) were studied using WRF/HYSPLIT model. The cluster analysis using observed winds from 28 weather stations during a year (2012) was performed in order to obtain representative local wind patterns. The cluster analysis identified eight local wind patterns (P1, P2, P3, P4-1, P4-2, P4-3, P4-4, P4-5) over the KNPP region. P1, P2 and P3 accounted for 14.5%, 27.0% and 14.5%, respectively. Both P1 and P2 are related to westerly/northwesterly synoptic flows in winter and P3 includes the Changma or typhoons days. The simulations of P1, P2 and P3 with high wind velocities and constant wind directions show that 137Cs emitted from the KNPP during 0900~1400 LST (Local Standard Time) are dispersed to the east sea, southeast sea and southwestern inland, respectively. On the other hands, 5 sub-category of P4 have various local wind distributions under weak synoptic forcing and accounted for less than 10% of all. While the simulated 137Cs for P4-2 is dispersed to southwest inland due to northeasterly flows, 137Cs dispersed northward for the other patterns. The simulated average 137Cs concentrations of each local wind pattern are 564.1~1076.3 Bqm-3. The highest average concentration appeared P4-4 due to dispersion in a narrow zone and weak wind environment. On the other hands, the lowest average concentration appeared P1 and P2 due to rapid dispersion to the sea. The simulated 137Cs concentrations and dispersion locations of each local wind pattern are different according to the local wind conditions.