Development of SEU-43 fuel bundle for CANDU type reactors

Annals of Nuclear Energy

Volumn 25, Issue 16, 1998, Pages 1363-1372

  Horhoianu, G ^a   Moscalu, D R ^a   Olteanu, G ^a   Ionescu, D V ^a  

^a INSTITUTE FOR NUCLEAR RESEARCH   (Romania)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 0032210812     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0306-4549(98)00025-5     Document Type: Article

References (12)

1. BOCZAR, P.G., McDONNEL, F.N., LANE, A.D., (1987), Slightly enriched uranium in CANDU an economic first step towards advanced fuel cycles, Proc. Int. Conf. on Nuclear Power Performance and Safety, IAEA, Vienna, Austria.
2. DOCA, L., DOCA, C., (1997), SEU-43 fuel bundle mechanical flow tests, Internal Report, No. 5102, INR Pitesti, Romania, in romanian.
3. EBERLE, R., HEINS, L., SONTHEIMER, F., (1994), Fuel Rod Analysis to Respond High Burnup and Demanding Loading Requirements, Proc. IAEA Tech. Comm. Meeting on Water Reactor Fuel Element Modelling at High Burnup and its Experimental Support, Bowness on Windermere, UK.
4. HORHOIANU, G., MOSCALU, D.R., OLTEANU, G., (1991), Preliminary SEU-43 fuel bundle design, Internal Report INR 3457, Pitesti, Romania, in romanian.
5. HORHOIANU, G., (1992), Improvement of the CANDU fuel element performance in order to increase the ability to operate at high powers and to meet high burnup, Final Report to IAEA research contract 6197/RB, INR Pitesti, Romania.
6. HORHOIANU, G., MOSCALU, D.R., (5-8 June 1990), Calculation study of the CANDU type fuel performance at extended burnup, International Conference on Fuel Performance at High Burnup for Water Reactors, Studsvik, Sweden, Procedings, pp. 191-196.
7. HORHOIANU, G., MOSCALU, D.R., (1990), CANDU type fuel element performance analysis by the probabilistic response surface method, Revue Roumaine Physique Tome 35, No 5-6, Bucharest, Romania.
8. HORHOIANU, G., MOSCALU, D. R., POPESCU, I. A., (1995), Fuel Rod Behaviour Analysis using ROFEM Fuel Performane Code, Trans. Int. KTG/ENS Topical Meeting on Nuclear Fuel, Wurzburg, Germany.
9. HORHOIANU, G., MOSCALU, D.R., POPESCU, I.A., (1996), Experimental aspects of load cycling capability of CANDU type nuclear fuel Annual Meeting on Nuclear Technology '96, Mannheim, Germany, Procedings, pp. 442-445.
10. LASLAU, P., SERGHIUTA, D., (1991), Reactor physics and thermal hydraulic calculations, Internal Report No. 3360, INR Pitesti, Romania, in romanian.
11. MOSCALU, D.R., HORHOIANU, G., (1991), Potential limiting factors for CANDU type fuel performance at extended burnup, Internal Report No. 3257, INR Pitesti, Romania, in romanian.
12. MOSCALU, D. R., (1995), On the Role of UO2 Thermal Conductivity Degradation at Extended Burnup In PHWR Fuels, Trans. Int. KTG/ENS Topical Meeting on Nuclear Fuel, Wurzburg, Germany, Procedings, pp. 96-100.