Advanced CANDU reactor

Hopwood, J.M., et al. (2003), Advanced CANDU Reactor An Optimized Energy Source of Oil Sands Application , GENES4/ANP2003 Conference, Japan, September, Paper 1199. 

The capital cost of nuclear fission will have dropped significantly— especially compared with that of the then-dinosaur-technology coal-fired generation. (As one example, today the capital costs of Advanced Candu Reactors are in the range of 1000 per kilowatt [kW]—about the same as coal-fired plants.) But since the operating cost of a nuclear power plant will always be a small fraction of that for a coal-fired power plant, the energy currencies from nuclear plants will be lower. 

Oil sands upgrading to the synthetic crude by adding nuclear hydrogen produced by advanced CANDU reactor (J. Hopwood - AECL, Ref. 7). 

The CANFLEX bundle design forms the basis of the both the fuel design adopted for LVRF (Section 15.7.2) and for the fuel design in the new 1000 MW Advanced CANDU Reactor. 

Advanced CANDU reactor (ACR-1000) Candu Energy Inc, (formerly AECL) — a member of the SNC-Lavalin Group... 

A new family of advanced nuclear reactors has been designed by the PWR, BWR, and CANDU suppliers, which are now (2006)... 

N.J. Spinks, N. Pontikakis and R.B. Duffey, Thermo-Economic Assessment of Advanced, High-Temperature CANDU Reactors , Proceedings of ICONE 10, 10 International Conference on Nuclear Engineering, Arlington, VA, April 14-18, 2002. 

Spinks, N.J., N. Pontikakis, and R.B. Duffey. 2002. Thermo-economic assessment of advanced, high-temperature CANDU reactors. In Proceedings of the 10th International Conference on Nuclear Engineering ICONE10), ICONElO-22433, AprU, Arlington, Virginia, USA. 

Boczar, P.G., P.S.W. Ghan, G.R. Dyck, and D.B. Buss. 1999. Recent Advances in Thorium Fuel Cycles for CANDU Reactors, Proceedings of the IAEA Technical Committee Meeting on Utilization of Thorium Fuel, November 17-19, Vienna, Austria. 

Figure VIII-1 shows a simplified schematic diagram of the nuclear steam supply system with the Package-Reactor. The concept resembles a calandria-type pressurized heavy water reactor (e.g., the FUGEN advanced thermal reactor (ATR) or CANDU reactors) since all these employ pressure tubes. But the Package-Reactor is somewhat different from the ATR or the CANDU. The Package-Reactor employs natural circulation with two-phase flow for core cooling and has no recirculation pumps. The height of the pressure tubes of the cassettes is required to be as low as possible to attain a compact unit. Two-phase flow with high void fractions similar to BWRs is adopted to attain natural circulation with a cassette height of 6 m and a fuel rod length of 3.65 m.

The following summarizes the approach by AECL to improve the safety of future CANDU reactors. As a general principle, the development objectives of advanced HWRs will be guided by the requirements of the operating utilities. 

The safety design objectives for advanced CANDU HWRs will be to continue the emphasis on defence in depth and evolutionary improvement to proven concepts that maximizes confidence in their safety to the public. The operational safety objectives during normal operation for future heavy water reactors include minimizing accident initiators and designing for ALARA (as low as reasonably achievable). Other operational improvement objectives include improved maintainability, standardization and simplification. 

S.J. Bushby, G. R. Dimmick, R. B. Duffery, et al., Conceptual Designs for Advanced, High-Temperature CANDU Reactors, Proc. lCONE-8, Baltimore, MD, April 2-6,2000, ICONE-8470 (2000)... 

A Catalogue of Advanced Fuel Cycles in CANDU-PHW Reactors, Veeder and Didsbury, Chalk River Nuclear Laboratories, Chalk River, Ontario, Canada, KOJ 1JO, 1985. 

The vast majority (80%) of the reactors mentioned are light-water-moderated reactors (LWR). The LWR subdivide in 60% PWR and 20% BWR. The remaining 20% of the reactors are divided among CANadian Deuterium Uranium reactor (CANDU), Reaktor Bolshoi Moshchnosti Kanalny (RBMK), large power channel reactor, gas-cooled reactor (GCR), advanced gas-cooled reactor (AGR), and fast breeder reactor (FBR). 

Dastur, A.R. and P.S.W. Chan. 1993. The Role of Enriched Uranium in CANDU Power Plant Optimization, Proceedings of the IAEA Technical Committee Meeting on Advances in Heavy Water Reactors, June 7-10, Toronto, Canada IAEA report lAEA-TECDOC-738 (1994 March). 

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