Calculation of dose rates in loss of coolant accident due to double ended rupture of the experimental tangential irradiation beam tube of MTR reactor. | ||
| Arab Journal of Nuclear Sciences and Applications | ||
| Article 7, Volume 55, Issue 1, January 2022, Pages 70-76 PDF (714.51 K) | ||
| Document Type: Original Article | ||
| DOI: 10.21608/ajnsa.2021.75275.1472 | ||
| Authors | ||
| Mahmoud aboelross* 1; esmat amin2; Magdy Zaky3; Abdallah Abdelsalam4; Wafaa Osman Bahr5 | ||
| 1Reactor Physics and Neutrons, Egyptian Atomic Energy Authority, Cairo, Egypt | ||
| 2Department of Nuclear Safety Engineering, Nuclear and Radiological Regulatory Authority, Cairo, Egypt | ||
| 3ETRR-2, EAEA, Egypt | ||
| 4Physics Department, Faculty of science,Cairo University,Cairo,Egypt. | ||
| 5Physics Department ,Faculty of Science,Cairo University,Cairo,Egypt | ||
| Abstract | ||
| A MTR reactor is an open water pool reactor type. The water pool serves as a shield from radioactive radiations. The most serious accident in this type of reactor is the Loss of Coolant Accident (LOCA) due to rupture either of a primary coolant pipe or of any experimental beam tube. In the present work it has been assumed that pool water drains out due to double ended rupture of the tangential irradiation beam tube (TIC) which has a diameter 150 mm. For an operating power level of 22 MW, the equilibrium core would enter into melting conditions if the pool drain time is less than one hour. It was also assumed that Emergency Core Cooling System (chimney water injection system and siphon effect breaker were not working. The reactor interiors have been modeled using the Monte Carlo N-Particle Transport code MCNPX 2.7.0. The source term has been determined using the ORIGEN-2 code. The doses and dose rates calculations in different places of operator (as phantom of Tissue-Equivalent Material) inside of the reactor building were determined by using Monte Carlo N-Particle Transport (MCNPX).The results show that the dose rate in the control room would be 5.24557 SV/h, the dose rate in the reactor hall above the pools on the gate would be7.20137 SV/h and the dose rate in the Emergency control room would be 2.68239 SV/h. Those dose rates are extremely high and would lead to fatal doses in short time. | ||
| Keywords | ||
| MTR; LOCA; TIC; MCNPX; ORIGEN; dose rate | ||
|
Statistics Article View: 1,002 PDF Download: 660 |
||
