earticle

논문검색

논문

A STUDY FOR DOSE DISTRIBUTION IN SPENT FUEL STORAGE POOL INDUCED BY NEUTRON AND GAMMA‐RAY EMITTED IN SPENT FUELS

원문정보

HEE DONG SOHN, JONG KYUNG KIM†

피인용수 : 0(자료제공 : 네이버학술정보)

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

저자정보

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

참고문헌

자료제공 : 네이버학술정보

    함께 이용한 논문

      0개의 논문이 장바구니에 담겼습니다.