Improvement of Few-Group Homogenized Cross-Sections for RSG-GAS In-Core Fuel Management Code Batan-FUEL-Reference-Cited by-同舟云学术

Improvement of Few-Group Homogenized Cross-Sections for RSG-GAS In-Core Fuel Management Code Batan-FUEL

Published:2023-02-08 Issue:3 Volume:9 Page:
ISSN:2332-8983
Container-title:Journal of Nuclear Engineering and Radiation Science
language:en
Short-container-title:

Author:

Pinem Surian¹,Hartanto Donny²,Liem Peng Hong³⁴,Luthfi Wahid⁵

Affiliation:

1. Research Center for Nuclear Reactor Technology, Research Organization for Nuclear Energy, National Research and Innovation Agency (BRIN), Building 80th Science and Technology Research Center (PUSPIPTEK) , South Tangerang 15314, Banten, Indonesia

2. Oak Ridge National Laboratory , One Bethel Valley Road, Oak Ridge, TN 37830

3. Cooperative Major in Nuclear Energy, Graduate School of Engineering, Tokyo City University (TCU) , 1-28-1, Tamazutsumi, Tokyo 158-8557, Setagaya, Japan ; , 416 Muramatsu, Tokaimura 319-1112, Ibaraki, Japan

4. Scientific Computational Division, Nippon Advanced Information Service (NAIS Co., Inc.) , 1-28-1, Tamazutsumi, Tokyo 158-8557, Setagaya, Japan ; , 416 Muramatsu, Tokaimura 319-1112, Ibaraki, Japan

5. Research Center for Nuclear Reactor Technology, Research Organization for Nuclear Energy, National Research and Innovation Agency (BRIN), 80th Building Science and Technology Research Center (PUSPIPTEK) South Tangerang 15314, Banten, Indonesia

Abstract

Abstract This paper presents the generation and the verification of the few-group homogenized cross section for Batan-FUEL code. This code is routinely used for fuel management in the G. A. Siwabessy Multipurpose Reactor (RSG-GAS). The Monte Carlo code Serpent 2 code, in conjunction with the latest nuclear data library ENDF/B-VIII.0, was used. Calculations using the existing newly generated few-group cross section data were carried out for the 88th core. The calculated core parameters such as excess reactivity and control rod worth are compared to the available experimental data. On the other hand, the fuel burnup fraction and radial power peaking factor (PPF) are compared to the results of Serpent 2. It was shown that the new cross section data have more consistency and a better agreement excess reactivity and control rod worth compared to the experimental data. Similarly, the U-235 burnup fraction and radial power peaking factor by the new cross section data are also shown to concur well with Serpent 2. The newly generated few-group cross section is recommended to replace the existing ones for the fuel management of RSG-GAS.

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Link

https://asmedigitalcollection.asme.org/nuclearengineering/article-pdf/9/3/031502/6979910/ners_009_03_031502.pdf

Reference20 articles.

1. Fuel management strategy for the new equilibrium silicide core design of RSG GAS (MPR-30)

2. Design of Transition Cores of RSG GAS (MPR-30) With Higher Loading Silicide Fuel;Nucl. Eng. Des.,2010

3. Neutronic Design of Mixed Oxide-Silicide Cores for the Core Conversion of RSG-GAS Reactor;Atom Indonesia,2001

4. Concept and Methods of the Program MAIN: Controlling the IAEFUEL Program Cycle for Neutronic Calculations Regarding Research Reactor,1986

5. Batan-Fuel: A General in-Core Fuel Management Code;Atom Indonesia,1996