Research output: Contribution to report/book/conference proceedings › In-proceedings paper

**MCNPX analysis of delayed neutron fraction in beryllium reflected cores.** / Kalcheva, Silva; Koonen, Edgar.

Research output: Contribution to report/book/conference proceedings › In-proceedings paper

Kalcheva, S & Koonen, E 2014, MCNPX analysis of delayed neutron fraction in beryllium reflected cores. in *Proceedings of the International Conference on Physics of Reactors : PHYSOR 2014.* 003 edn, vol. 2014, JAEA-Conf, JAEA - Japan Atomic Energy Agency, pp. 1-20.

Kalcheva, S., & Koonen, E. (2014). MCNPX analysis of delayed neutron fraction in beryllium reflected cores. In *Proceedings of the International Conference on Physics of Reactors : PHYSOR 2014 *(003 ed., Vol. 2014, pp. 1-20). (JAEA-Conf). JAEA - Japan Atomic Energy Agency.

Kalcheva S, Koonen E. MCNPX analysis of delayed neutron fraction in beryllium reflected cores. In Proceedings of the International Conference on Physics of Reactors : PHYSOR 2014. 003 ed. Vol. 2014. JAEA - Japan Atomic Energy Agency. 2014. p. 1-20. (JAEA-Conf).

@inproceedings{7adeb8e7b666421988878cf325631bb7,

title = "MCNPX analysis of delayed neutron fraction in beryllium reflected cores",

abstract = "The behavior of the effective delayed neutron and effective delayed photo neutron fractions in beryllium reflected cores is investigated. An MCNPX analysis of the dependence of the effective beta fractions on the fuel depletion is performed for different fuel types. An alternative method for estimation of the delayed neutron fraction during the reactor operating, avoiding double criticality simulation on prompt neutrons only (k_p), is compared to the standard MCNP approach (1-k_p/k_p_+_d). The methodology is based on MCNP tally calculations of fission integrals and actual delayed neutron fraction, β_m{"}k, for each fissile isotope m({"}2{"}3{"}5U, {"}2{"}3{"}9Pu, {"}2{"}4{"}1Pu) in a given reactor configuration and fuel type k. The methodology is verified on a generic infinite lattice and after that applied for the MCNP whole core model of the BR2 reactor at different depletion steps during the reactor operation.",

keywords = "Effective delayed neutron fraction, Delayed neutron effectiveness, Photo neutrons, MC NPX 2.7.0., Beryllium reflector",

author = "Silva Kalcheva and Edgar Koonen",

note = "Score=3",

year = "2014",

month = "9",

day = "28",

language = "English",

volume = "2014",

series = "JAEA-Conf",

publisher = "JAEA - Japan Atomic Energy Agency",

pages = "1--20",

booktitle = "Proceedings of the International Conference on Physics of Reactors",

address = "Japan",

edition = "003",

}

TY - GEN

T1 - MCNPX analysis of delayed neutron fraction in beryllium reflected cores

AU - Kalcheva, Silva

AU - Koonen, Edgar

N1 - Score=3

PY - 2014/9/28

Y1 - 2014/9/28

N2 - The behavior of the effective delayed neutron and effective delayed photo neutron fractions in beryllium reflected cores is investigated. An MCNPX analysis of the dependence of the effective beta fractions on the fuel depletion is performed for different fuel types. An alternative method for estimation of the delayed neutron fraction during the reactor operating, avoiding double criticality simulation on prompt neutrons only (k_p), is compared to the standard MCNP approach (1-k_p/k_p_+_d). The methodology is based on MCNP tally calculations of fission integrals and actual delayed neutron fraction, β_m"k, for each fissile isotope m("2"3"5U, "2"3"9Pu, "2"4"1Pu) in a given reactor configuration and fuel type k. The methodology is verified on a generic infinite lattice and after that applied for the MCNP whole core model of the BR2 reactor at different depletion steps during the reactor operation.

AB - The behavior of the effective delayed neutron and effective delayed photo neutron fractions in beryllium reflected cores is investigated. An MCNPX analysis of the dependence of the effective beta fractions on the fuel depletion is performed for different fuel types. An alternative method for estimation of the delayed neutron fraction during the reactor operating, avoiding double criticality simulation on prompt neutrons only (k_p), is compared to the standard MCNP approach (1-k_p/k_p_+_d). The methodology is based on MCNP tally calculations of fission integrals and actual delayed neutron fraction, β_m"k, for each fissile isotope m("2"3"5U, "2"3"9Pu, "2"4"1Pu) in a given reactor configuration and fuel type k. The methodology is verified on a generic infinite lattice and after that applied for the MCNP whole core model of the BR2 reactor at different depletion steps during the reactor operation.

KW - Effective delayed neutron fraction

KW - Delayed neutron effectiveness

KW - Photo neutrons

KW - MC NPX 2.7.0.

KW - Beryllium reflector

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/38148597

M3 - In-proceedings paper

VL - 2014

T3 - JAEA-Conf

SP - 1

EP - 20

BT - Proceedings of the International Conference on Physics of Reactors

PB - JAEA - Japan Atomic Energy Agency

ER -

ID: 6814403