Analysis of Fission Products’ Release in Pebble-Bed High-Temperature Gas-Cooled Reactor Fuel Elements Using a Modified FRESCO II Numerical Model

The radiation safety design and emergency analysis of an advanced nuclear system highly depends on the source term analysis results. In modular high-temperature gas-cooled reactors (HTGRs), the release rates of fission products (FPs) from fuel elements are the key issue of source term analysis. The...

Full description

Saved in:
Bibliographic Details
Main Authors: Chao Fang, Chuan Li, Jianzhu Cao, Ke Liu, Sheng Fang
Format: Article
Language:English
Published: Wiley 2021-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2021/6627789
Tags: Add Tag
No Tags, Be the first to tag this record!
_version_ 1832561756481781760
author Chao Fang
Chuan Li
Jianzhu Cao
Ke Liu
Sheng Fang
author_facet Chao Fang
Chuan Li
Jianzhu Cao
Ke Liu
Sheng Fang
author_sort Chao Fang
collection DOAJ
description The radiation safety design and emergency analysis of an advanced nuclear system highly depends on the source term analysis results. In modular high-temperature gas-cooled reactors (HTGRs), the release rates of fission products (FPs) from fuel elements are the key issue of source term analysis. The FRESCO-II code has been established as a useful tool to simulate the accumulation and transport behaviors of FPs for many years. However, it has been found that the mathematical method of this code is not comprehensive, resulting in large errors for short-lived nuclides and large time step during calculations. In this study, we used the original model of TRISO particles and spherical fuel elements and provided a new method to amend the FRESCO-II code. The results show that, for long-lived radionuclides (Cs-137), the two methods are perfectly consistent with each other, while in the case of short-lived radionuclides (Cs-138), the difference can be more than 1%. Furthermore, the matrix method is used to solve the final release rates of FPs from fuel elements. The improved analysis code can also be applied to the source term analysis of other HTGRs.
format Article
id doaj-art-2eb58e1ac0ea4c399fb6e00e93a4105d
institution Kabale University
issn 1687-6075
1687-6083
language English
publishDate 2021-01-01
publisher Wiley
record_format Article
series Science and Technology of Nuclear Installations
spelling doaj-art-2eb58e1ac0ea4c399fb6e00e93a4105d2025-02-03T01:24:12ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832021-01-01202110.1155/2021/66277896627789Analysis of Fission Products’ Release in Pebble-Bed High-Temperature Gas-Cooled Reactor Fuel Elements Using a Modified FRESCO II Numerical ModelChao Fang0Chuan Li1Jianzhu Cao2Ke Liu3Sheng Fang4Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, ChinaThe radiation safety design and emergency analysis of an advanced nuclear system highly depends on the source term analysis results. In modular high-temperature gas-cooled reactors (HTGRs), the release rates of fission products (FPs) from fuel elements are the key issue of source term analysis. The FRESCO-II code has been established as a useful tool to simulate the accumulation and transport behaviors of FPs for many years. However, it has been found that the mathematical method of this code is not comprehensive, resulting in large errors for short-lived nuclides and large time step during calculations. In this study, we used the original model of TRISO particles and spherical fuel elements and provided a new method to amend the FRESCO-II code. The results show that, for long-lived radionuclides (Cs-137), the two methods are perfectly consistent with each other, while in the case of short-lived radionuclides (Cs-138), the difference can be more than 1%. Furthermore, the matrix method is used to solve the final release rates of FPs from fuel elements. The improved analysis code can also be applied to the source term analysis of other HTGRs.http://dx.doi.org/10.1155/2021/6627789
spellingShingle Chao Fang
Chuan Li
Jianzhu Cao
Ke Liu
Sheng Fang
Analysis of Fission Products’ Release in Pebble-Bed High-Temperature Gas-Cooled Reactor Fuel Elements Using a Modified FRESCO II Numerical Model
Science and Technology of Nuclear Installations
title Analysis of Fission Products’ Release in Pebble-Bed High-Temperature Gas-Cooled Reactor Fuel Elements Using a Modified FRESCO II Numerical Model
title_full Analysis of Fission Products’ Release in Pebble-Bed High-Temperature Gas-Cooled Reactor Fuel Elements Using a Modified FRESCO II Numerical Model
title_fullStr Analysis of Fission Products’ Release in Pebble-Bed High-Temperature Gas-Cooled Reactor Fuel Elements Using a Modified FRESCO II Numerical Model
title_full_unstemmed Analysis of Fission Products’ Release in Pebble-Bed High-Temperature Gas-Cooled Reactor Fuel Elements Using a Modified FRESCO II Numerical Model
title_short Analysis of Fission Products’ Release in Pebble-Bed High-Temperature Gas-Cooled Reactor Fuel Elements Using a Modified FRESCO II Numerical Model
title_sort analysis of fission products release in pebble bed high temperature gas cooled reactor fuel elements using a modified fresco ii numerical model
url http://dx.doi.org/10.1155/2021/6627789
work_keys_str_mv AT chaofang analysisoffissionproductsreleaseinpebblebedhightemperaturegascooledreactorfuelelementsusingamodifiedfrescoiinumericalmodel
AT chuanli analysisoffissionproductsreleaseinpebblebedhightemperaturegascooledreactorfuelelementsusingamodifiedfrescoiinumericalmodel
AT jianzhucao analysisoffissionproductsreleaseinpebblebedhightemperaturegascooledreactorfuelelementsusingamodifiedfrescoiinumericalmodel
AT keliu analysisoffissionproductsreleaseinpebblebedhightemperaturegascooledreactorfuelelementsusingamodifiedfrescoiinumericalmodel
AT shengfang analysisoffissionproductsreleaseinpebblebedhightemperaturegascooledreactorfuelelementsusingamodifiedfrescoiinumericalmodel