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-eigenvalue perturbation in Monte Carlo calculationTuya, D.; Nagaya, Yasunobu
Annals of Nuclear Energy, 169, p.108919_1 - 108919_9, 2022/05
Times Cited Count：1 Percentile：29.26(Nuclear Science & Technology)Estimating an effect of a perturbation in a fissile system on its -eigenvalue requires special technique called perturbation theory when the considered perturbation is small. In this study, we develop an adjoint-weighted correlated sampling (AWCS) method based on the exact perturbation theory without any approximation by combining the correlated sampling (CS) method with iterated-fission probability (IFP) based adjoint-weighting method. With the advantages of the CS method being good at providing very small uncertainty for small perturbations and the IFP-based adjoint-weighting method being suitable for continuous-energy Monte Carlo calculation, the developed AWCS method based on the exact perturbation theory offers a new rigorous approach for perturbation calculations. The obtained results by the developed AWCS method for verification problems involving Godiva and simplified STACY density perturbations showed good agreement with the reference calculations.
Sugino, Kazuteru; Takino, Kazuo
JAEA-Data/Code 2019-011, 110 Pages, 2020/01
JAEA-Data-Code-2019-011.pdf:3.37MB
A deterministic discrete ordinates method (SN method) transport calculation code for three-dimensional hexagonal geometry has been developed as the MINISTRI code (Ver. 7.0). MINISTRI is based on the triangle-mesh finite difference method, which can perform neutron transport calculations with high accuracy for cores of fast power reactors and assemblies of the Russian BFS critical facility. The present study has derived a proper scheme for remarkably improving the convergence of MINISTRI by investigating the issue of previous MINISTRI (Ver. 1.1), which sometimes plays a poor convergence performance in calculations for large-scale power reactor cores. The verification test of improved MINISTRI has been carried out for various cores by setting the reference result as the multi-group Monte-Carlo calculation with the same cross-sections as used in MINISTRI. As a result, it is found that the agreements are within 0.1% for eigenvalues and within 0.7% for power distributions. Thus, the satisfying accuracy of MINISTRI has been confirmed. In order to reduce the calculation time, the initial diffusion calculation scheme and the parallel processing have been implemented. As a result, the calculation time is reduced to the approximately one tenth compared with previous MINISTRI. Furthermore, adoption of the treatment of the anisotropic cell streaming effect, preparation of the perturbation calculation tool, implementation of the function for specification of the triangle-mesh-wise material and merging of the hexagonal-mesh calculation code MINIHEX have been carried out. Thus, the versatility of MINISTRI has been enhanced.
Tachi, Yukio; Ochs, M.*
Progress in Nuclear Science and Technology (Internet), 5, p.229 - 232, 2018/11
Various types of post-accident radioactive waste have been generated from cleanup and decommissioning activities at the Fukushima Daiichi Nuclear Power Plant. For the disposal of these wastes, perturbation effects resulting from co-existing substances (e.g., organic substances, boron, and salts) are needed to be considered. Such co-existing substances may influence on the radionuclide sorption parameters for the safety assessment of the disposal systems. The present study focuses on developing the methodology to quantify sorption parameters by considering such perturbation effects and illustrating example calculations regarding the sorption reduction factors (SRFs) due to the presence of organic ligands (ISA) for cement systems. Three approaches for the derivations of SRFs for cement-Am-ISA case were compared. These options should be applied as a stepwise manner according to the data availability for the perturbation effects resulting from the co-existing substances.
Ochs, M.*; Vriens, B.*; Tachi, Yukio
Progress in Nuclear Science and Technology (Internet), 5, p.208 - 212, 2018/11
The clean-up activities related to the accident at the Fukushima Nuclear Power Plant give rise to several types of wastes containing cementitious materials, such as concrete. Further, the use of cement-based barriers may be considered, due to their favorable and stable chemical properties, including their ability to sorb or incorporate radionuclides. Wastes from Fukushima are expected to contain substances that can have perturbing effects on retention, especially organic complexing substances, boron, and chloride salts. The present study focuses on a methodology for quantifying the retention behaviour of UVI) and U(IV) in cement materials of different degradation and in the presence of organics, boron, and salts on the basis of available literature information. A stepwise approach is proposed and illustrated for Kd setting for U(VI) and U(IV).
Nagaya, Yasunobu
Proceedings of Joint International Conference on Mathematics and Computation, Supercomputing in Nuclear Applications and the Monte Carlo Method (M&C + SNA + MC 2015) (CD-ROM), 9 Pages, 2015/04
A new method to calculate the prompt neutron decay constant (
) with the Monte Carlo method is proposed. It is based on the conventional - search algorithm but no iteration is required for the value search. The eigenvalue is expressed in the truncated Taylor series with regard to ; the differential coefficients are calculated with the differential operator sampling, which is one of the Monte Carlo perturbation techniques. In order to examine the applicability of the proposed method, verification has been performed for simple geometries of a bare fast system (Godiva) and an unreflected thermal system (STACY). Comparisons has been done with the pulsed neutron source (PNS) simulation and the direct calculation from the definition of the value. The results with the proposed method show good agreement with the reference PNS simulation.
Nagaya, Yasunobu; Mori, Takamasa
Journal of Nuclear Science and Technology, 42(5), p.428 - 441, 2005/05
Times Cited Count：61 Percentile：95.82(Nuclear Science & Technology)A new method to estimate a change in the effective multiplication factor due to the perturbed fission source distribution has been proposed for Monte Carlo perturbation calculations with the correlated sampling and differential operator sampling techniques. The method has been implemented into the MVP code for verification. Simple benchmark problems have been set up for fast and thermal systems and the applicability of the method has been verified with the problems. In consequence, it has been confirmed that the method is very effective to estimate the change. It has been also shown that there are some cases where the perturbed source effect is significant and the change in reactivity cannot be estimated accurately without taking the effect into account. Even in such cases, the new method can estimate the perturbed source effect and the estimation of the change in reactivity has been remarkably improved.
Mikhailovskii, A. B.*; Churikov, A. P.*; Konovalov, S. V.; Shirokov, M. S.*; Tsypin, V. S.*
Doklady Physics, 48(4), p.159 - 162, 2003/04
Times Cited Count：1 Percentile：12.86(Mechanics)It is shown that there is a new class of perturbations, limiting the pressure of ideally stable plasma in the conditions of fusion reactors of tokamak type. localization of such modes includes three characteristic regions: large-scale (MHD), Larmor and sub-Larmor ones. It is suggested that these modes can be responsible for spontaneous generation of neoclassical tearing modes observed experimentally.
Yoshino, Ryuji; D.J.Campbell*; E.Fredrickson*; Fujisawa, Noboru; N.Granetz*; Gruber, O.*; T.C.Hender*; D.A.Humphreys*; N.Ivanov*; S.Jardin*; et al.
Fusion Energy 2000 (CD-ROM), 4 Pages, 2001/05
no abstracts in English
Kobayashi, M.*; Tsuda, Takashi; Tashiro, Kenji*; Kojima, H.*; Zhai, K.*; Takamura, Shuichi*
Nuclear Fusion, 40(2), p.181 - 193, 2000/02
Times Cited Count：27 Percentile：63.03(Physics, Fluids & Plasmas)no abstracts in English
Nagaya, Yasunobu; Mori, Takamasa
Proceedings of the ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR2000) (CD-ROM), p.13 - 0, 2000/00
no abstracts in English
Tokuda, Shinji; Yoshino, Ryuji
Nuclear Fusion, 39(9), p.1123 - 1132, 1999/09
Times Cited Count：21 Percentile：56.36(Physics, Fluids & Plasmas)no abstracts in English
Tokuda, Shinji; *
JAERI-Data/Code 98-032, 36 Pages, 1998/11
JAERI-Data-Code-98-032.pdf:1.93MB
no abstracts in English
C and Pu sample worths in FCA assembly XVII-1Nagaya, Yasunobu; Ono, Akio; Osugi, Toshitaka
JAERI-Research 95-003, 40 Pages, 1995/01
JAERI-Research-95-003.pdf:1.37MB
no abstracts in English
Akino, Fujiyoshi; Takeuchi, Motoyoshi; Ono, Toshihiko
Journal of Nuclear Science and Technology, 31(8), p.861 - 863, 1994/08
Times Cited Count：4 Percentile：53.92(Nuclear Science & Technology)no abstracts in English
*; *; Kikuchi, Yasuyuki
JAERI-M 84-027, 31 Pages, 1984/02
no abstracts in English
Journal of the Physical Society of Japan, 53(5), p.1587 - 1589, 1984/00
Times Cited Count：1 Percentile：40.66(Physics, Multidisciplinary)no abstracts in English
*; ;
JAERI-M 82-147, 25 Pages, 1982/11
no abstracts in English
Yoshida, H.; ; ; Sengoku, Seio; ; ; ;
JAERI-M 9789, 28 Pages, 1981/11
no abstracts in English
; ; *; *
JAERI-M 9473, 105 Pages, 1981/05
no abstracts in English
