Inferring the reactivity in accelerator driven systems: Corrective spatial factors for Source-Jerk and area methods

Deterministic and Monte Carlo modeling and analyses of YALINA-THERMAL subcritical assembly.

“…The kinetic method can only be applied by MCNP/MCNPX computer code since it has the explicit representation of the delayed neutrons. In the static method, 18 the integrals over time of the prompt and the total reaction rates are tallied by two separate simulations, which model the neutron source as time independent. The static method can be applied by either MCNP/MCNPX or PARTISN codes.…”

“…[1][2][3][4][5][6][7] These transmuters are referred to as Accelerators Driven Systems (ADS). Research programs for partitioning and transmuting nuclear waste by ADS are under development in Japan, [8][9][10][11] China, 12 Europe, [13][14][15][16][17][18][19][20][21][22][23][24][25][26][27][28][29][30][31] and Russia. [32][33][34] In Europe, the MUSE program was carried out at the MASURCA facility in Cadarache, France.…”

“…[32][33][34] In Europe, the MUSE program was carried out at the MASURCA facility in Cadarache, France. [13][14][15][16][17][18][19] The MASURCA facility consists of a fast subcritical reactor, loaded with MOX fuel and sodium, coupled with a deuteron accelerator, and it operated at low power of less than 5 kW. Another set of experiments has been carried out within the TRIGA Accelerator Driven Experiment (TRADE) program.…”

Monte Carlo modeling and analyses of YALINA- booster subcritical assembly Part II : pulsed neutron source.

“…In order to compare the numerical and experimental multiplication factor a correction factor has been introduced following the procedure suggested by Bell and Glasstone 26 and applied by Gabrielli et al [27][28] The correction factor is the ratio between the numerical MCNP k eff (calculated in criticality mode) and the numerical MCNP/C k eff (calculated in source mode) obtained by the area method. When the correction factor is multiplied to the experimental results obtained by the area method, the discrepancy with the MCNP k eff reduces to less than 430 pcm, as shown in Table II.…”

Accelerator-induced transients in Accelerator Driven Subcritical Reactors

“…In this study, pulsed beam operation is revisited to illustrate the possible use of pulsed operation to measure the reactivity of the core of an ADSR accurately. Previous studies have shown that core reactivity can be measured using approaches such as the source-jerk method, area method and current-to-flux indicator [10,4]. These methods require a change in the neutron flux to be able to measure the reactivity.…”