球床型氟盐冷却高温堆的初步中子学分析

Zhifeng Li; Changyou Zhao; Guangchun Zhang; Song Han; Jie Huang

doi:10.13832/j.jnpe.2021.02.0197

球床型氟盐冷却高温堆的初步中子学分析

Translated title of the contribution: Preliminary Neutronics Analysis for Fluorine-Salt-Cooled Pebble-Bed Reactor

Zhifeng Li
, Changyou Zhao
, Guangchun Zhang^*
, Song Han
, Jie Huang

^*Corresponding author for this work

China General Nuclear Power Group
National University of Defense Technology

Research output: Contribution to journal › Article › peer-review

1 Scopus citations

Abstract

In order to obtain the key neutronics parameters of the pebble-bed fluoride-salt-cooled high-temperature reactor (PB-FHR), the random packing method is used to obtain the coordinates of the three layers of isotropic coated particles (TRISO) particles, and the discrete element method is adopted to the coordinates of the fuel pebbles within the active core. Then the neutron transport calculated is conducted by the Monte Carlo code to analyze the effects of the fuel random distribution on the core neutronics parameters. The calculation results showed that the effects of the random distribution on the multiplication coefficient, group cross section and active core fuel pebble power can be neglected. Based on the above results, the nuclear design of the pebble-bed fluoride-salt-cooled high-temperature reactor can be simplified.

Translated title of the contribution	Preliminary Neutronics Analysis for Fluorine-Salt-Cooled Pebble-Bed Reactor
Original language	Chinese (Traditional)
Pages (from-to)	197-201
Number of pages	5
Journal	Hedongli Gongcheng/Nuclear Power Engineering
Volume	42
Issue number	2
DOIs	https://doi.org/10.13832/j.jnpe.2021.02.0197
State	Published - 15 Apr 2021
Externally published	Yes

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10.13832/j.jnpe.2021.02.0197

Cite this

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title = "球床型氟盐冷却高温堆的初步中子学分析",

abstract = "In order to obtain the key neutronics parameters of the pebble-bed fluoride-salt-cooled high-temperature reactor (PB-FHR), the random packing method is used to obtain the coordinates of the three layers of isotropic coated particles (TRISO) particles, and the discrete element method is adopted to the coordinates of the fuel pebbles within the active core. Then the neutron transport calculated is conducted by the Monte Carlo code to analyze the effects of the fuel random distribution on the core neutronics parameters. The calculation results showed that the effects of the random distribution on the multiplication coefficient, group cross section and active core fuel pebble power can be neglected. Based on the above results, the nuclear design of the pebble-bed fluoride-salt-cooled high-temperature reactor can be simplified.",

keywords = "Fuel pebble power, Group cross sections, Multiplication coefficient, Pebble-bed fluoride-salt-cooled high-temperature reactor, Random distribution",

author = "Zhifeng Li and Changyou Zhao and Guangchun Zhang and Song Han and Jie Huang",

year = "2021",

month = apr,

day = "15",

doi = "10.13832/j.jnpe.2021.02.0197",

language = "繁体中文",

volume = "42",

pages = "197--201",

journal = "Hedongli Gongcheng/Nuclear Power Engineering",

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publisher = "Atomic Energy Press",

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}

TY - JOUR

T1 - 球床型氟盐冷却高温堆的初步中子学分析

AU - Li, Zhifeng

AU - Zhao, Changyou

AU - Zhang, Guangchun

AU - Han, Song

AU - Huang, Jie

PY - 2021/4/15

Y1 - 2021/4/15

N2 - In order to obtain the key neutronics parameters of the pebble-bed fluoride-salt-cooled high-temperature reactor (PB-FHR), the random packing method is used to obtain the coordinates of the three layers of isotropic coated particles (TRISO) particles, and the discrete element method is adopted to the coordinates of the fuel pebbles within the active core. Then the neutron transport calculated is conducted by the Monte Carlo code to analyze the effects of the fuel random distribution on the core neutronics parameters. The calculation results showed that the effects of the random distribution on the multiplication coefficient, group cross section and active core fuel pebble power can be neglected. Based on the above results, the nuclear design of the pebble-bed fluoride-salt-cooled high-temperature reactor can be simplified.

AB - In order to obtain the key neutronics parameters of the pebble-bed fluoride-salt-cooled high-temperature reactor (PB-FHR), the random packing method is used to obtain the coordinates of the three layers of isotropic coated particles (TRISO) particles, and the discrete element method is adopted to the coordinates of the fuel pebbles within the active core. Then the neutron transport calculated is conducted by the Monte Carlo code to analyze the effects of the fuel random distribution on the core neutronics parameters. The calculation results showed that the effects of the random distribution on the multiplication coefficient, group cross section and active core fuel pebble power can be neglected. Based on the above results, the nuclear design of the pebble-bed fluoride-salt-cooled high-temperature reactor can be simplified.

KW - Fuel pebble power

KW - Group cross sections

KW - Multiplication coefficient

KW - Pebble-bed fluoride-salt-cooled high-temperature reactor

KW - Random distribution

UR - https://www.scopus.com/pages/publications/85104533589

U2 - 10.13832/j.jnpe.2021.02.0197

DO - 10.13832/j.jnpe.2021.02.0197

M3 - 文章

AN - SCOPUS:85104533589

SN - 0258-0926

VL - 42

SP - 197

EP - 201

JO - Hedongli Gongcheng/Nuclear Power Engineering

JF - Hedongli Gongcheng/Nuclear Power Engineering

IS - 2

ER -

球床型氟盐冷却高温堆的初步中子学分析

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