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Items where Author is "Rozon, Daniel"

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Number of items: 18.

B

Boubcher, M., Marleau, G., & Rozon, D. (1999, May). Development of an isotopic depletion method for reactor core calculations [Paper]. Communicating the nuclear advantage. 39th Annual Canadian Nuclear Association Conference & 20th Annual Canadian Nuclear Society Conference, Montréal, Québec. Unavailable

Boubcher, M., Marleau, G., & Rozon, D. (1998, October). Pseudo-isotopes generation for the ²³⁵U and ²³⁸U depletion chains [Paper]. 19th Annual Conference of the Canadian Nuclear Society, Toronto, Ontario (Canada). Unavailable

C

Chambon, R., Varin, E., & Rozon, D. (2007). Candu Fuel Management Optimization Using Alternative Gradient Methods. Annals of Nuclear Energy, 34(12), 1002-1013. External link

Chambon, R., Varin, É., & Rozon, D. (2023, June). CANDU fuel management optimization using generalized perturbation theory in the donjon diffusion code [Paper]. CNS 2005 Annuel Conference, Toronto. Unavailable

M

Marleau, G., Noceir, S., Roy, R., & Rozon, D. (1997, June). Dragon modelling of the SLOWPOKE-2 reactor at École Polytechnique [Paper]. 1997 Canadian Nuclear Society Conference, Toronto, Can. Unavailable

N

Noceir, S., El Hajjaji, O., Varin, É., Roy, R., & Rozon, D. (1997, June). Diffusion calculations for the SLOWPOKE-2 reactor using DONJON [Paper]. 1997 Canadian Nuclear Society Conference, Toronto, Can. Unavailable

R

Rozon, D., & Shen, W. (2001). A Parametric Study of the Dupic Fuel Cycle to Reflect Pressurized Water Reactor Fuel Management Strategy. Nuclear Science and Engineering, 138(1), 1-25. External link

Rozon, D., & Shen, W. (1998, October). Comparison of slightly enriched uranium fuel and MOX fuel in CANDU-6 reactor [Paper]. Canadian Nuclear Society 19th annual conference, Toronto, Ontario (Canada). Published in Annual Conference Proceedings. Canadian Nuclear Society, 19(2). Unavailable

Rozon, D., Varin, É., Roy, R., & Brissette, D. Generalized perturbation theory estimates of zone level response to refueling perturbations in a CANDU 600 reactor [Paper]. Advances in nuclear fuel management II : topical meeting. Unavailable

Rozon, D., & Kaveh, S. (1997, June). SLOWKIN: A simplified model for the simulation of reactor transients in SLOWPOKE-2 [Paper]. 1997 Canadian Nuclear Society Conference, Toronto, Can. Unavailable

Rozon, D., Roy, R., & Varin, É. (1995, June). DRAGON/OPTEX predictions of channel power peaking factors and average exit burnup in CANDU-6 [Paper]. 1995 Annual Meeting of American Nuclear Society, Philadelphia, PA. Published in Transactions of the American Nuclear Society, 72. Unavailable

Roy, R., Marleau, G., Tajmouati, J., & Rozon, D. (1994). Modelling of CANDU reactivity control devices with the lattice code DRAGON. Annals of Nuclear Energy, 21(2), 115-132. External link

S

Sissaoui, M. T., Marleau, G., & Rozon, D. (1999). CANDU Reactor Simulations Using the Feedback Model With Actinide Burnup History. Nuclear Technology, 125(2), 197-212. External link

Shen, W., & Rozon, D. (1999, May). Effect of PWRA fuel management strategy on DUPIC fuel cycle [Paper]. Communicating the nuclear advantage. 39th Annual Canadian Nuclear Association Conference & 20th Annual Canadian Nuclear Society Conference, Montréal, Québec. Unavailable

Shen, W., & Rozon, D. (1998, October). Generation of consistent nuclear properties of DUPIC fuel by DRAGON with ENDF/B-VI nuclear data library [Paper]. Canadian Nuclear Society 19th annual conference, Toronto, Ontario (Canada). Published in Annual Conference Proceedings. Canadian Nuclear Society, 19(2). External link

Shen, W., Rozon, D., & Marleau, G. Parametric analysis of Doppler coefficient of reactivity in DUPIC fuel by DRAGON [Paper]. 19th Annual Conference of the Canadian Nuclear Society. Unavailable

Shen, W., & Rozon, D. (1998, October). Study of DUPIC fuel cycle in CANDU 6 reactor by DRAGON/DONJON [Paper]. International Conference on the Physics of Nuclear Science and Technology, Long Island, NY. Unavailable

Sissaoui, M. T., Marleau, G., & Rozon, D. Accounting for actinide burnup history in CANDU reactor simulations [Paper]. Advances in nuclear fuel management II : topical meeting. Unavailable

List generated on: Sat Mar 2 02:12:07 2024 EST