• Nuclear Engineering and Technology
• /
• v.3 no.4
• /
• pp.203-208
• /
• 1971

Noether's theorem is applied to the one dimensional neutron transport equation. It is obtained the transformation rendering the functional of the one dimensional Boltzmann equation invariant. It is derived the law conserving the product of the directional flux and its adjoint flux. The possible types of the solution of the Boltzmann equation are discussed. The results are compared with the well-known solution.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1997.10a
• /
• pp.115-120
• /
• 1997

영광3호기 방사선관리구역에 대한 중성자선량률을 정확히 평가하기 위하여 MCNP4A 전산코드를 이용, 방사선관리구역에서의 중성자 스펙트럼 계산을 수행하였다. 영광3호기에 대한 보다 정확하고 정밀한 3차원 몬테칼로 모델을 구축하기 위하여 핵연료집합체 구성요소 및 원자로심을 둘러싸고 있는 baffle, barrel,압력용기 등을 정확하게 묘사하였으며, 특히 방사선관리구역 주위의 구조물에 대해서도 3자원 MCNP 모델을 구축함으로써 원자로심부터 방사선관리구역까지 완전한 몬테칼로 모사(full-scope Monte Carlo simulation)를 이용한 계산을 수행하였다. 계산결과는 에너지 구간에 따른 중성자속 스펙트럼으로 나타내었으며 이 결과를 바탕으로 중성자속에 대한 선량률 환산인자를 고려하여 중성자선량률을 계산할 수 있다.

• Nuclear Engineering and Technology
• /
• v.17 no.2
• /
• pp.105-115
• /
• 1985

The axial height-dependent transverse buckling is derived from 3-dimensional depletion file in steadystate conditions. For transient conditions a physical correlation is developed based on the linear relationship existing between the responses of in-core and ex-core detectors. The use of this model greatly improves the reliability of a 1-dimensional diffusion theory program in Predicting the axial power transients accompanying large variations of control rod positions.

• Nuclear Engineering and Technology
• /
• v.11 no.4
• /
• pp.275-286
• /
• 1979

In 600 MWe CANDU-PHW reactors PMCR will be used on-site for calibration of the regional overpower system. PMCR will be executed off-line in one of the station computers. The program calculates accurate channel power maps by incorporating a fuel turnup dependent flux to power conversion algorithm. Fuel turnup is calculated by PMCR, hence it is independent of other software. Extensive comparisons with the uniform flux/power conversion approximations were made. Significant improvements in power mapping accuracy are achieved with PMCR.

• Proceedings of the Korean Nuclear Society Conference
• /
• 2004.10a
• /
• pp.1101-1102
• /
• 2004

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2009.11a
• /
• pp.103-104
• /
• 2009

• Proceedings of the Korean Nuclear Society Conference
• /
• 2003.05a
• /
• pp.102.2-102.2
• /
• 2003

• Proceedings of the Korea Society for Energy Engineering kosee Conference
• /
• 2001.05a
• /
• pp.81-88
• /
• 2001

• Proceedings of the Korean Nuclear Society Conference
• /
• 1999.05a
• /
• pp.29-29
• /
• 1999

• Proceedings of the Korean Nuclear Society Conference
• /
• 2002.05a
• /
• pp.443.1-443
• /
• 2002