New RMC Energy Deposition Treatment and its Application in Multi-Physics Simulation

Author:

Luo Hao1,Li Kaiwen2,An Nan1,Huang Shanfang1ORCID,Wang Kan1

Affiliation:

1. Tsinghua University, Department of Engineering Physics, Haidian, Beijing 100084, China

2. Tsinghua University, Institute of Nuclear and New Energy Technology, Haidian, Beijing 100084, China

Funder

National Key Research and Development Project of China

Publisher

Informa UK Limited

Reference26 articles.

1. D. BROWN, “ENDF-6 Formats Manual—Data Formats and Procedures for the Evaluated Nuclear Data Files ENDF/B-VI, ENDF/B-VII and ENDF/B-VIII,” Brookhaven National Laboratory (2023).

2. ENDF/B-VIII. 0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-Project Cross Sections, New Standards and Thermal Scattering Data;BROWN D. A.;Nucl. Data Sheets,2018

3. RMC – A Monte Carlo code for reactor core analysis

4. D. GRIESHEIMER et al., “MC21 V. 6.0—A Continuous-Energy Monte Carlo Particle Transport Code with Integrated Reactor Feedback Capabilities,”Proc. Joint Int. Conf. Supercomputing in Nuclear Applications and Monte Carlo (SNA + MC 2013), Paris, France, October 27–31, 2013, EDP Sciences (2014).

5. Serpent—A Continuous-Energy Monte Carlo Reactor Physics Burnup Calculation Code;LEPPÄNEN J.;VTT Technical Research Centre of Finland,2013

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