Development of Monte Carlo Neutron Transport Method-Based Supercritical Transient Code with Time-Dependent Feedback Capability-Reference-Cited by-同舟云学术

Development of Monte Carlo Neutron Transport Method-Based Supercritical Transient Code with Time-Dependent Feedback Capability

Published:2018-12-04 Issue:5 Volume:193 Page:481-494
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Tuya Delgersaikhan¹,Obara Toru¹

Affiliation:

1. Tokyo Institute of Technology, Institute of Innovative Research, Laboratory for Advanced Nuclear Energy, Ookayama 2-12-1-N1-19, Meguro-ku, Tokyo 152-8550, Japan

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295639.2018.1540209

Reference22 articles.

1. Transient Fission Matrix: Kinetic calculation and kinetic parameters βeff and Λeff calculation

2. Dynamic Monte Carlo Method for Nuclear Reactor Kinetics Calculations

3. Developing and investigating a pure Monte-Carlo module for transient neutron transport analysis

4. J. LEPPANEN, “Development of a Dynamic Simulation Mode in SERPENT 2 Monte Carlo Code,” Proc. Int. Conf. Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2013), Sun Valley, Idaho, May 5–9. 2013, p. 117, American Nuclear Society (2013).

5. Methods for calculating coupled reactor systems

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