Fast neutron fluence calculations as support for a BWR pressure vessel and internals surveillance program

Crack growth rate in core shroud horizontal welds using two models for a BWR

“…7, no crack arrest is predicted. Table 1 shows the fluences E > 1 MeV (n/m 2 ) calculated after the 9th and 11th refueling outages (RFO's) for a Mexican 2027 MWt BWR, using the accumulated fast neutron fluence profile on three weld locations (H3, H4 and H5) on the core shroud, calculated by Lucatero et al [13].…”

“…Then the corrected stress intensity factor for the weld residual stresses, for a circumferential crack is given as: Table 1 Accumulated fast neutron fluence on two weld locations on the core shroud [13]. …”

Experimental Validation of Ex-Vessel Neutron Spectrum by Means of Dosimeter Materials Activation Method

“…Precise knowledge of neutron energy spectrum is imperative to various fundamental and experimental studies in many field of nuclear physics, nuclear engineering and technology, medical sciences, and health physics research [8][9][10][11][12][13][14][15][16]. An accurate description of neutron spectrum is needed for understanding a reactor's characteristics and evaluating the quantity of neutron irradiation effect on reactor components such as fuel and materials [1,[17][18][19][20].…”

“…The dosimeter material activation technique is a basic method for determination of neutron doses internal to the reactor core and around reactor vessel [9,21,22], especially for the determination of neutron flux, the characteristics of neutrons in the core, and the characterizations of fuel, materials, and other components, as well as for reactor safety study [2,[23][24][25]. The accuracy enhancement of neutron spectrum measurement is still a major issue in the reactor dosimetry research, in order to improve the accuracy of determination of the neutron spectrum, especially in reflector and reactor vessel area, and to verify the results of reactor surveilance program [26][27][28][29][30][31].…”