By Luigi Massimo
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Additional info for Physics of High-Temperature Reactors
Example text
Neutrons can indeed be thought as forming a kind of a gas whose treatment is simplified by the fact that neutrons do not interact with each other. The general time, position and angle-dependent form of the transport equation is dN(r,E Ci,t) ot = _ nVN(r? 1) where the symbols mean: v neutron velocity corresponding to energy E, N neutron angular density, 2 t total neutron cross-sections (generally function of r and E), S neutron source, r space coordinate, Ω unit vector in the direction of the neutron motion, E energy, t time, XS(E'-*E, Ω'-*Ω) scattering cross-section from E', Ω' into E, Ω.
B E L L and S. , 1970. 3. B. G. C A R L S O N and K. D. L A T H R O P , Transport theory—the method of discrete ordinates. In Computing Methods in Reactor Physics ; edited by H. G R E E N S P A N , C. K E L B E R and D. O K R E N T , Gordon & Breach, 1968. 4. M. M. M E R R I L L , Nuclear design methods and experimental data in use at Gulf General Atomic, Gulf-Ga-A 12652 (GA-LTR-2), July 1973. 5. K. D. L A T H R O P , DTF-IV, a Fortran-IV program for solving the multigroup transport equation with anisotropie scattering, LA-3373, 12 Nov.
5. K. D. L A T H R O P , DTF-IV, a Fortran-IV program for solving the multigroup transport equation with anisotropie scattering, LA-3373, 12 Nov. 1965. 6. K. D. L A T H R O P and F. W. B R I N K L E Y , Theory and use of the general geometry TWOTRAN program, LA-4432, May 1970. 7. S. F R A N C E S C O N , The Winfrith DSN programme, AEEW-R273. 8. L. M A S S I M O , A programme for the solution of the monoenergetical transport equation in the P 5 approximation for a multiregion cylindrical geometry, EUR-2584e, 1965.