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Determination of the neutron fluence in the welding of the 'Core shroud' of the BWR reactor core; Determinacion de la fluencia neutronica en las soldaduras del 'core shroud' del nucleo de un reactor BWR

Abstract

With the purpose of defining the inspection frequency, in function of the embrittlement of the materials that compose the welding of the 'Core Shroud' or encircling of the core of a BWR type reactor, is necessary to know the neutron fluence received for this welding. In the work the calculated values of neutron fluence accumulated maxim (E > 1 MeV) during the first 8 operation cycles of the reactor are presented. The calculations were carried out according to the NRC Regulatory Guide 1.190, making use of the DORT code, which solves the transport equation in discreet ordinate in two dimensions (xy, r{theta}, and rz). The results in 3D were obtained applying the Synthesis method according to the guide before mentioned. Results are presented for the horizontal welding H3, H4, and H5, showing the corresponding curves to the fluence accumulated to the cycle 8 and a projection for the cycle 14 is presented. (Author)
Authors:
Lucatero, M A; Xolocostli M, J V; Gomez T, A M; Palacios H, J C [1] 
  1. ININ, 52750 Ocoyoacac, Estado de mexico (Mexico)
Publication Date:
Jul 01, 2006
Product Type:
Conference
Report Number:
INIS-MX-2162
Resource Relation:
Conference: 1. american congress of the IRPA; 7. regional congress of radiological and nuclear safety; 24. annual meeting of the SMSR; 17. annual congress of the SNM, Retos y tendencias para el continente americano respecto a la proteccion radiologica, la seguridad nuclear y el ambiente, Acapulco, Gro. (Mexico), 3-8 Sep 2006
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BURNUP; BWR TYPE REACTORS; COORDINATES; D CODES; DENSITY; DIAGRAMS; DIMENSIONS; EQUATIONS; EXPERIMENTAL DATA; FREQUENCY DEPENDENCE; FUEL ASSEMBLIES; GEOMETRY; INSPECTION; MEV RANGE; MONTE CARLO METHOD; NEUTRON FLUENCE; O CODES; SHROUDS; SOLDERING
OSTI ID:
20846073
Research Organizations:
International Radiation Protection Association (IRPA) (France); Sociedad Mexicana de Seguridad Radiologica A.C. (SMSR), Mexico D.F. (Mexico); Sociedad Nuclear Mexicana (SNM), Mexico D.F. (Mexico); Organismo Internacional de Energia Atomica (OIEA), Vienna (Australia); Federacion de Radioproteccion de America Latina y el Caribe (FRALC), Zacatecas (Mexico); Organizacion Panamericana de la Salud (OPS), Washington, D.C. (United States)
Country of Origin:
Mexico
Language:
Spanish
Other Identifying Numbers:
TRN: MX0700049018272
Availability:
Available from INIS in electronic form
Submitting Site:
MXN
Size:
13 pages
Announcement Date:
Mar 29, 2007

Citation Formats

Lucatero, M A, Xolocostli M, J V, Gomez T, A M, and Palacios H, J C. Determination of the neutron fluence in the welding of the 'Core shroud' of the BWR reactor core; Determinacion de la fluencia neutronica en las soldaduras del 'core shroud' del nucleo de un reactor BWR. Mexico: N. p., 2006. Web.
Lucatero, M A, Xolocostli M, J V, Gomez T, A M, & Palacios H, J C. Determination of the neutron fluence in the welding of the 'Core shroud' of the BWR reactor core; Determinacion de la fluencia neutronica en las soldaduras del 'core shroud' del nucleo de un reactor BWR. Mexico.
Lucatero, M A, Xolocostli M, J V, Gomez T, A M, and Palacios H, J C. 2006. "Determination of the neutron fluence in the welding of the 'Core shroud' of the BWR reactor core; Determinacion de la fluencia neutronica en las soldaduras del 'core shroud' del nucleo de un reactor BWR." Mexico.
@misc{etde_20846073,
title = {Determination of the neutron fluence in the welding of the 'Core shroud' of the BWR reactor core; Determinacion de la fluencia neutronica en las soldaduras del 'core shroud' del nucleo de un reactor BWR}
author = {Lucatero, M A, Xolocostli M, J V, Gomez T, A M, and Palacios H, J C}
abstractNote = {With the purpose of defining the inspection frequency, in function of the embrittlement of the materials that compose the welding of the 'Core Shroud' or encircling of the core of a BWR type reactor, is necessary to know the neutron fluence received for this welding. In the work the calculated values of neutron fluence accumulated maxim (E > 1 MeV) during the first 8 operation cycles of the reactor are presented. The calculations were carried out according to the NRC Regulatory Guide 1.190, making use of the DORT code, which solves the transport equation in discreet ordinate in two dimensions (xy, r{theta}, and rz). The results in 3D were obtained applying the Synthesis method according to the guide before mentioned. Results are presented for the horizontal welding H3, H4, and H5, showing the corresponding curves to the fluence accumulated to the cycle 8 and a projection for the cycle 14 is presented. (Author)}
place = {Mexico}
year = {2006}
month = {Jul}
}