Criticality calculations for the spent fuel storage pools for Etrr_1 and Etrr_2 reactors

Nukleonika

Volumn 45, Issue 2, 2000, Pages 141-144

  Aziz, Moustafa ^a   Andrzejewski, Krzysztof ^b  

^a Nuclear Centre   (Egypt)

^b INSTITUTE OF ATOMIC ENERGY   (Poland)

Author keywords

Criticality safety; Research reactors

Indexed keywords

EID: 0039032400     PISSN: 00295922     EISSN: None     Source Type: Journal    
DOI: None     Document Type: Article

References (9)

1. Briesmeister JF (1993) MCNP 4A - a general Monte Carlo n-particle transport code, LA-12625-M
2. Fowler TB, Vondy DR, Cunningham GW (1971) CITATION -Nuclear Reactor Core Analysis Code, ORNL_TM-2496
3. Merelle EC, Tas A (1992) Spent fuel storage. TECDOC-643, Vol. 5. IAEA, Vienna, pp 143-147
4. Nakagome Y, Kanda K, Shibata T (1992) KURRI: Fresh fuel storage. TECDOC-643, Vol. 5. IAEA, Vienna, pp 137-142
5. NEA DATA BANK Documentation 1507/01 (1996)
6. Pesic MP (1998) Criticality safety of fresh HEU fuel at the RA reactor. 2nd International Topical Meeting on Research Reactor Fuel Management, March 29-31,1998, Bruges, Belgium. European Nuclear Society, Bruges, pp 123-136
7. Ponde RB, Matos JE (1992) Nuclear criticality assessment of LEU and HEU fuel element storage. TECDOC-643, Vol. 5. IAEA, Vienna, pp 119-136
8. Safety Analysis Report of ETRR_1 reactor (1996) AEA, Cairo
9. Safety Analysis Report of ETRR_2 reactor (1997) AEA, Cairo