Advances in Nuclear Science and Technology by M. D. Brough, C. T. Chudley (auth.), Jeffery Lewins, Martin

By M. D. Brough, C. T. Chudley (auth.), Jeffery Lewins, Martin Becker (eds.)

The Editors get pleasure from proposing an additional vol­ ume of their Annual overview sequence. the current quantity con­ tains six papers which may be acknowledged to span from the speculation of layout to the perform of operation of contemporary nuclear strength stations, consequently targeting nuclear strength as a resource of electric energy. beginning with the main mathem­ atical, and continuing towards expertise, we've got the Chudley and Brough account of a brand new interpretation of (linear) Boltzmann shipping conception when it comes to the attribute or ray procedure. This appears to be like new in program the following, yet in fact the strategy is the kid of many classical experiences within the answer of partial differen­ tial equations and proves to remarkably well-suited to trendy pcs and their numerical bases. we'd positioned the item by way of Dickson and Doncals at the layout of heterogeneous cores subsequent, with its value for quick reactors of the long run. many of the "central worthy" discrepancies, with their implication for safeguard and relia­ bility based on, inter alia, the Doppler influence, have made this an important zone for answer: to determine that we will strengthen layout tools and codes that may reconcile conception and exper,. . . iment to the purpose at which theoretical designs might be authorized for construction with out the necessity for a full-scale mock­ up, as needed to be performed within the 1950's for the sunshine water re­ actors.

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And Brissenden, R. , "Some Improvements in the DSN Method of B. Carlson for Solving the Neutron Transport Equation," AEEW-Rl6l, 1963, 6. Askew, J. , "Some Boundary Condition Problems Arising in the Application of Collision Probability Methods," Proceedings of the Vienna Seminar, Page 343, 1972. 7. Brough, M. , "The CACTUS Code," (to be published). 8. Askew, J. , private conununica tion. 9. , 14, Page 295, 1962. 10. Askew, J. , "A Characteristics Formulation of the Neutron Transport Equation in Complicated Geometries," Atomic Energy Establishment, Winfrith Report Mll08, 1972.

8, would then specify a group and ~ angle. 8) then corresponds to both inner and outer iteration. , negative region numbers). The bulk of the work of finding the required solution could be carried out, therefore, on a very simple processor that had access to this tracked data. It might be that true parallel or array processing could be used for this. ACKNOWLEDGMENTS We should like to acknowledge an enormous debt to Dr. John Askew at AEE Winfrith for suggesting this problem and for his unfailing support and advice during its solution.

It is clearly a necessary condition that the method should predict experimental results correctly, but it is not sufficient. A similar situation exists when comparing the predictions of the model in cases where an exact solution is known. , all neutrons at the same speed, separate isotropic kernel, etc. Again, it is necessary that a new method reproduces these results, but hardly sufficient. Fortunately, at just the time the problem of testing this particular method occurred, a readymade solution occurred.

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