Earticle

초록

영어

The objective of this study is to recommend the radiation protection design parameters from the shielding point of view for concrete wall between the decay tank room and the primary pump room in TRIGA Mark-II Research Reactor Facility. The shield design for this concrete wall has been performed with the help of Point-kernel Shielding Code Micro-Shield 5.05 and this design was also validated based on the measured dose rate values with Radiation Survey Meter (G-M Counter) considering the ICRP-60 (1990) recommendations for occupational dose rate limit (10 μSv/hr). The recommended shield design parameters are: (i) thickness of 114.3 cm Ilmenite-Magnetite Concrete (IMC) or 129.54 cm Ordinary Reinforced Concrete (ORC) for concrete wall A (ii) thickness of 66.04 cm Ilmenite-Magnetite Concrete (IMC) or 78.74 cm Ordinary Reinforced Concrete (ORC) for concrete wall B and (iii) door thickness of 3.175 cm Mild Steel (MS) on the entrance of decay tank room. In shielding efficiency analysis, the use of I-M concrete in the design of this concrete wall shows that it reduced the dose rate by a factor of at least 3.52 times
approximately compared to ordinary reinforced concrete.

목차

Abstract
 1. INTRODUCTION
 2. CALCULATIONAL TECHNIQUES
 3. DESCRIPTION OF SOURCE AND SHIELD MATERIALS
  3.1 Description of Source
  3.2 Shield Materials
 4. LAYOUT PLAN OF THE CONCRETE WALL
 5. RESULTS AND DISCUSSIONS
 6. CONCLUSION
 REFERENCES

키워드

저자

• M J H Khan [ Atomic Energy Research Establishment ] Corresponding author
• M Rahman [ Atomic Energy Research Establishment ]
• F U Ahmed [ Bangladesh Atomic Energy Commission, Bangladesh ]
• S I Bhuiyan [ Bangladesh Atomic Energy Commission, Bangladesh ]
• A Haque [ Atomic Energy Research Establishment ]
• A Zulquarnain [ Atomic Energy Research Establishment ]

참고문헌

발행기관

간행물

표지보기 관심저널 등록

• 간행물명

  방사선방어학회지 [Journal of Radiation Protection and Research]

• 간기

  계간

• pISSN

  2508-1888

• 수록기간

  1976~2026

• 등재여부

  KCI 등재,SCOPUS

• 십진분류

  KDC 559 DDC 629