Nuclear Engineering and Technology
- Volume 10 Issue 2
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- Pages.87-92
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- 1978
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- 1738-5733(pISSN)
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- 2234-358X(eISSN)
Multigroup Calculations for TRIGA-type Reactor Analysis
- Lee, Jong-Tai (Korea Atomic Energy Research Institute) ;
- Kim, Jung-Do (Korea Atomic Energy Research Institute) ;
- Mann Cho (Korea Atomic Energy Research Institute)
- Published : 1978.06.01
Abstract
Multigroup constant calculation system for TRIGA-type reactor analysis was provided. Calculations for initial criticality, temperature coefficient, flux and power distributions of TRICA-Mark III reactor were carried out by using diffusion code CITATION. And some of results were compared with the values of start-up experiments and design values. It could be confirmed that the prepared computation system is very useful for TRIGA-type reactor analysis.
TRIGA형 원자로를 해석하기 위한 다군 군정수 계산 조직을 따련하고 확산코드 CITATION에 의한 2차원 계산을 통해 TRIGA-Mark III 원자로의 초기임계치, 온도계수, 중성자속 및 출력분포 등을 계산하였다. 일부 계산결과를 임계실험 및 설계치와 비교 검토하였다. 마련된 계산체계가 만족한 결과를 얻을 수 있음이 입증되었다.
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