Variational methods and speed-up of Monte Carlo perturbation computations for optimal design in nuclear systems

Abstract

ham mad YAQUB 3 1 De part ment of Mechatronics En gi neer ing, Air Uni ver sity, Islamabad, Pa ki stan 2 De part ment of Math e mat ics, Na tional Uni ver sity of Com puter and Emerg ing Sci ences, Islamabad, Pa ki stan 3 De part ment of Math e mat ics, Riphah In ter na tional Uni ver sity, Islamabad, Pa ki stan Sci en tific pa per

A new methodology for determination of water of crystallization for uranyl nitrate samples using scanning electron microscope, energy dispersive X-ray, and MCPN-5

“…The gen eral Monte Carlo code (MCNP-5) was used to com pute the ab so lute ef fi ciency of the de tec tor [6,7]. The char ac ter is tics and spec i fi ca tions of the pla -nar HPGe de tec tor and tested NM were mod eled [8], and 40 in put files were cre ated to run for these cal cu lations.…”

“…The CR for en ergy line (185.7 keV), with ac compa ny ing un cer tain ties, s CR , at dif fer ent en rich ment values of the tested NM, are given in ta bles (4)- (7). Ta ble 4 shows the re la tion ship be tween the cal cu lated CR us ing MCNP-5, tested NM en rich ment and the mass of U-235.…”

“…The same trend is also re marked in tabs. (5)- (7). In ra di a tion spec tros copy, it is im por tant to produce math e mat i cal cal i bra tion curves for ra di a tion detec tors.…”

Optimal design of a nuclear power plant condenser control system based on multi-objective optimization algorithm

“…Con sid er ing the ra pid ity and sta bil ity of the three con trol sys tems, in this pa per the time-do main per formance in dex, ISTE, based on er ror in te gral is taken as the op ti mi za tion ob jec tive. The op ti mi za tion de sign meth ods of a nu clear power sys tem in clude Monte Carlo method [2], neu ral net work method [3], and intel li gent op ti mi za tion al go rithm [4]. An in tel li gent opti mi za tion al go rithm named multi-ob jec tive par ti cle swarm op ti mi za tion (MOPSO) [5] based on Pareto dom i nance con cept is adopted to op ti mize the con trol pa ram e ters, thus a good con trol qual ity of the con trol sys tem can be ob tained.…”

Three-dimensional time-dependent neutron diffusion simulation using average current nodal expansion method

“…The de sign and safety as sess ment of new nu clear sys tems sug gested for fu ture im prove ment need ac curate sim u la tion of the be hav ior of neu tron dis tri bu tion dur ing typ i cal op er a tional and ac ci den tal con di tions [1]. Gen er ally, two dif fer ent strat e gies have been usually used for ob tain ing neu tron flux dis tri bu tion in a nuclear re ac tor core in clud ing the de ter min is tic meth ods, e. g. the nodal method [2], and the proba bil is tic methods, e. g. the Monte Carlo method [3,4]. As the nu mer ical ex per i ments noted in [5] and oth ers, re vealed in suffi cient ac cu racy of the point-re ac tor model for the anal y sis of large ther mal light wa ter re ac tors (LWR) [6], ap prox i ma tion strat e gies for solv ing the space-en ergy de pend ent neu tron ki net ics equa tions have been of inter est in re ac tor phys ics ever since early 1960.…”