Cracking effect on gamma-ray shielding performance in concrete structure

Progress in Nuclear Energy

Volumn 49, Issue 4, 2007, Pages 303-312

  Lee, Chang Min ^a   Lee, Yoon Hee ^a   Lee, Kun Jai ^a  

^a Korea Advanced Institute of Science and Technology (KAIST)   (South Korea)

Author keywords

Collinear crack; Concrete; Crack effect; Dry storage; Measuring system; Shielding performance

Indexed keywords

CODES (STANDARDS); CONCRETE CONSTRUCTION; CRACK INITIATION; HYDRATION; RADIATION SHIELDING; THERMAL STRESS;

COLLINEAR CRACKS; CRACK EFFECTS; DRY STORAGE; MEASURING SYSTEM; SHIELDING PERFORMANCE;

GAMMA RAYS;

EID: 34248674028     PISSN: 01491970     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.pnucene.2007.01.006     Document Type: Article

References (17)

1. Broadhead, B.L., 2002. Estimation of the dose effect of gamma-ray streaming thorough cracks in the MVST storage/disposal cask. In: Twelfth Biennial RPSD Topical Meeting.
2. CANBERRA, 1993. A high throughput segmented gamma scanning system for automatic waste assay, application note.
3. Dean M.H., and Stedeford B. Leakage through gaps around shielding windows in radiotherapy treatment rooms. Phys. Med. Biol. 29 (1984) 711-718
4. DOE, 1989. Final version dry cask storage study, DOE/RW-02, Department of Energy.
5. Fillmore, Denzel L., Winston, Pholip L., Morton, Sheryl L., Hoffman, Cecelia R., 2005. The long-term performance of concrete in nuclear applications. In: Proceedings of PVP2005, 2005 ASME Pressure Vessels and Piping Division Conference, PVP2005-71743.
6. Jung, J.Y., 1998. Status of onsite spent fuel storage. In: Nuclear Industry, Korea Atomic Industrial Forum, November 1998, Seoul, Korea, p. 56 (in Korean).
7. Kalos, Malvin H., Whitlock, Paula A., 2000. MCNP-4C general Monte Carlo N-particle transport code, Oak Ridge Laboratory.
8. Kim, Y.Y., Kim, J.S., Kim, J.K., 2005. The mechanic character of the ECC (engineered cementitious composite) designed by micromechanics. A collection of papers by Korea Concrete Institute, vol. 17, pp. 709-716 (in Korean).
9. Knoll G.F. Radiation Detection and Measurement. third ed. (2000), John Wiley & Sons Inc.
10. Korea Concrete Institute, 2004. Concrete standard specifications, Korea Concrete Institute.
11. MOCIE, 1998. The fourth long-term power development plan (1998-2015), MOCIE, South Korea (in Korean).
12. MOST, 2002. Nuclear statistics and general status, Ministry of Science and Technology (MOST), South Korea (in Korean).
13. NETEC, 2003. Development of consolidated dry storage system for CANDU spent fuel, Korea Hydro Nuclear Power Co. (in Korean).
14. Oh, B.W., 2005, New concrete engineering, Korea Concrete Institute (in Korean).
15. Okumura, A., Shirai, K., Saegusa, T., 2001. R&D program for interim storage of spent fuel in CRIEPI. In: Spring JNMM Proceedings, pp. 12-17.
16. Sorenson J.A., and Phelps M.E. Physics in Nuclear Medicine. second ed. (1987), W.B. Saunders Company
17. Whang H.C. Non-destructive Examination. Gold Press (2004) (in Korean)