Abramov B.D.
     Institute for Physics and Power Engineering, Obninsk, Russia
 
   Some reactor kinetics mathematical
modelling problems are considered in the framework of the standard 6-
group delayed neutron constants (Keepin, ABBN, JENDL, ENDF/B6) with
energy and isotope dependent precursor half-lives, and the new 8-group
delayed neutron data (Spriggs, Campbell, Piksaikin) with "universal"
precursor decay constant (or half-life) groups identical for all isotopes and
energies. 
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neutron transport equations and thermohydraulic transient and emergency processes in 
fast reactors, Preprint IPPE-2637, Obninsk, 1997.
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Voprosy atomnoj nauki i tekhniki, Ser. Yadernye konstanty, No. 1, p. 59-98 (1996).
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ABBN-93 constants system, Voprosy atomnoj nauki i tekhniki, Ser. Yadernye 
konstanty, No. 1, p. 21 (1998).
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of Delayed Neutrons, Nucl. Sci. Eng., 114, 342 (1993).
22. Spriggs, G.D., Campbell, I.M., Piksaikin, V.M., An 8-Group Neutron Model Based on a 
Consistent Set of Half-Lives, Report LA-UR-98-1619, LANL, Distributed to the 
OECD/NEA-s Working Party in Delayed Neutrons (WPEC/SG6), 1999.
23. Piksaikin, V.M., Kazakov, L.E., Isaev, S.G., Korolev, G.G., Roshchenko, V.A., 
Tertychnyj, R.G., 8-group relative delayed neutron yields for monoenergetic neutron 
induced fission of 239Pu, Voprosy atomnoj nauki i tekhniki, Ser. Yadernye konstanty, 
No. 1, p. 66-67 (2001).
24. Piksaikin, V.M., Kazakov, L.E., Isaev, S.G., Korolev, G.G., Roshchenko, V.A., 
Tertychnyj, R.G., 8-group relative delayed neutron yields for epithermal neutron 
induced fission of 238U and 239Pu, ibid, p. 67-72 (2001).
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Neutrons from Thermal Neutron Induced Fission on 235U and Its Analytical 
Approximation, Voprosy atomnoj nauki i tekhniki, Ser. Yadernye konstanty, No. 1, 
p. 87-93 (2001).
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curves during thermal neutron fission, Voprosy atomnoj nauki i tekhniki, Ser. Yadernye 
konstanty, No. 2, p. 5-11 (1999).
27. Updated Codes and Methods to Reduce the Calculational Uncertainties of the LMFR 
Reactivity Effects, Working Material, First Research Co-ordination Meeting, Vienna, 
24-26 November 1999, p.11.
28. Abramov, B.D., Some questions on mathematical modelling of reactor kinetics, Preprint 
IPPE-2778, Obninsk, 1999.
29. Abramov, B.D., Danilychev, A.V., Stogov, V.Yu., Suslov, I.P., Questions on modelling 
the kinetics of heterogeneous regions with various types of fuel using point 
approximation, Preprint IPPE-2855, Obninsk, 2000.
30. Abramov, B.D., Some generalizations of reactor kinetics equations, Preprint IPPE-2875, 
Obninsk, 2001.
31. Abramov, B.D., Some modifications to the theory of coupled reactors, Atomnaya 
energiya, Vol. 90, No. 5, p. 337-345 (2001).
32. Abramov, B.D., Some modifications to point kinetics equations, Yadernaya energetika, 
No. 2, p. 52-59 (2001).
33. Abramov, B.D., Some generalizations of reactor inverse kinetics equations, Preprint 
IPPE-2970, Obninsk, 2003.