179
Views
2
CrossRef citations to date
0
Altmetric
Technical Note

Evaluation of Fuel Reactivity Worth Measurement in the Prototype Fast Reactor Monju

, , &
Pages 1619-1633 | Received 29 Nov 2021, Accepted 17 Feb 2022, Published online: 27 May 2022

References

  • “Guideline for Credibility Assessment of Nuclear Simulations,” AESJ-SC-A008:2015, Atomic Energy Society of Japan (2016) (in Japanese).
  • K. OHGAMA et al., “Model Verification and Validation Procedure for a Neutronics Design Methodology of Next Generation Fast Reactor,” Proc. ICAPP2017, Fukui-Kyoto, Japan, April 24–28, 2017.
  • T. HAZAMA et al., “Criticality Evaluation for the Monju Restart Core,” Nucl. Technol., 179, 250 (2012); https://doi.org/10.13182/NT12-A14097.
  • K. TAKANO et al., “Control Rod Worth Evaluation for the Monju Restart Core,” Nucl. Technol., 179, 266 (2012); https://doi.org/10.13182/NT12-A14098.
  • T. MOURI et al., “Isothermal Temperature Coefficient Evaluation for the Monju Restart Core,” Nucl. Technol., 179, 286 (2012); https://doi.org/10.13182/NT12-A14099.
  • A. KITANO, A. TAKEGOSHI, and T. HAZAMA, “Measurement and Analysis of Feedback Reactivity in the Monju Restart Core,” J. Nucl. Sci. Technol., 53, 7, 992 (2016); https://doi.org/10.1080/00223131.2015.1086705.
  • K. OHGAMA et al., “A Validation Study of a Neutronics Design Methodology for Fast Reactors Using Reaction Rate Distribution Measurements in the Prototype Fast Reactor Monju,” Proc. ICAPP2019, Juan-Les-Pins, France, May 12–15, 2019.
  • K. OHGAMA et al., “Evaluation of Fixed Absorber Reactivity Measurement in the Prototype Fast Reactor Monju,” Nucl. Technol., 207, 12, 1810 (2021); https://doi.org/10.1080/00295450.2020.1846481.
  • “International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhE),” NEA/NSC/DOC (2006), Organisation for Economic Co-operation and Development Nuclear Energy Agency (2010).
  • A. HARA et al., “SAGEP: Two-Dimensional Sensitivity Analysis Code Based on Generalized Perturbation Theory,” JAERI-M 84-027, Japan Atomic Energy Research Institute (1984) (in Japanese).
  • R. J. TUTTLE, “Delayed-Neutron Data for Reactor-Physics Analysis,” Nucl. Sci. Eng., 56, 37 (1975); https://doi.org/10.13182/NSE75-A26620.
  • K. L. DERSTINE, “DIF3D: A Code to Solve One-, Two-, and Three-Dimensional Finite-Difference Diffusion Theory Problems,” ANL-82-64, Argonne National Laboratory (1984).
  • T. HAZAMA et al., “Development of a Fine and Ultra-Fine Group Cell Calculation Code SLAROM-UF for Fast Reactor Analyses,” J. Nucl. Sci. Technol., 43, 908 (2006); https://doi.org/10.1080/18811248.2006.9711176.
  • K. SHIBATA et al., “JENDL-4.0: A New Library for Nuclear Science and Engineering,” J. Nucl. Sci. Technol., 48, 1 (2011); https://doi.org/10.1080/18811248.2011.9711675.
  • T. HAZAMA et al., “SLARO-UF:Ultra Fine Group Cell Calculation Code for Fast Reactor–Version 20090113-1,” JAEA-Review 2009-003, Japan Atomic Energy Agency (2009).
  • R. E. ALCOUFFE et al., “PARTISN: A Time-Dependent, Parallel Neutral Particle Transport Code System,” LA-UR-05-3925, Los Alamos National Laboratory (2005).
  • Y. NAGAYA et al., “MVP/GMVPII: General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculations Based on Continuous Energy and Multi-Group Methods,” JAERI 1348, Japan Atomic Energy Research Institute (2005).

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.