Earticle

초록

영어

With the reactor operation conditions ‐ 4.3 wt% 235U initial enrichment, burn‐up 55,000 MWd/MTU, average power 34 MW/MTU for three periods burned time for 539.2 days per period and cooling time for 100 hours after shut down, to set up the condition to determine the minimum height (depth) of spent fuel storage pool to shut off the radiation out of the spent fuel storage pool and to store spent fuels safely, the dose rate on the specific position directed to the surface of spent fuel storage pool induced by the neutron and gamma‐ray from spent fuels are evaluated. The length of spent fuel is 381 cm, and as the result of evaluation on each position from the top of spent fuel to the surface of spent fuel storage pool, it is difficult for neutrons from spent fuels to pass through the water layer of maximum 219 cm (600 cm from the floor of spent fuel storage pool) and 419 cm (800 cm from the floor of spent fuel storage pool) for gamma‐ray. Therefore, neutron and gamma‐ray from spent fuels can pass through below 419 cm (800 cm from the floor) water layer directed to the surface of spent fuel storage pool.

목차

Abstract
 1. INTRODUCTION
 2. MATERIAL AND METHODOLOGY
  2.1 Fuel Assembly
  2.2 Spent Fuel Storage Rack [3]
  2.3 Spent Fuel Storage Pool
  2.4 Computer Code and Cross Section Library
  2.5 Analysis Condition
 3. RESULTS AND DISCUSSION
  3.1 Nuclides Composition in Spent Fuel
  3.2 Neutron Dose Rate at Specified Position in Spent Fuel Storage Pool
  3.3 Gamma‐ray Dose Rate at Specified Position in Spent Fuel Storage Pool
  3.4 Total Dose Rate at Specified Position in Spent Fuel Storage Pool
 4. CONCLUSION
 REFERENCES

키워드

저자

• HEE DONG SOHN [ Doosan Heavy Industries & Construction ] Cprresponding author
• JONG KYUNG KIM† [ Nuclear Engineering Hanyang University Seoul ]

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