Published April 2016 | Version v1
Book Metadata-only

Preliminary simulation of the HTR-10 power raising test

Creators

  • 1. Institute of Nuclear and New Energy Technology, Tsinghua University, Collaborative Innovation Center of Advanced Nuclear Energy Technology, the Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Beijing (China)

Description

The 10 MW High Temperature Gas-cooled Reactor-Test Module (HTR-10) is the first high temperature gas-cooled reactor in China. The power raising test is a very important commissioning test of the HTR-10, since its results demonstrate the practicability and validity of the power regulation methods. Based on the actual test conditions, the power raising test is simulated using the THERMIX code and the simulation puts the emphasis on main parameters of the primary circuit. Regarding the reactor power, the helium pressure and the hot helium temperature, the calculation results agree well with the test ones, thus the simulation capability of THERMIX are fully validated. During the test process, the maximum fuel center temperature is always below the safety limit of 1230 ℃. (authors)

Part of:
Progress report on nuclear science and technology in China (Vol.4). Proceedings of academic annual meeting of China Nuclear Society in 2015, No.3--nuclear energy & power sub-volume

Additional details

Publishing Information

Publisher
Atomic Energy Press
Imprint Place
Beijing (China)
ISBN
978-7-5022-7103-9
Imprint Title
Progress report on nuclear science and technology in China (Vol.4). Proceedings of academic annual meeting of China Nuclear Society in 2015, No.3--nuclear energy & power sub-volume
Imprint Pagination
427 p.
Journal Page Range
p. 694-698

Conference

Title
2015 academic annual meeting of China Nuclear Society
Dates
21-24 Sep 2015
Place
Mianyang (China)

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
53084999
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CHINA; COMMISSIONING; FUELS; HELIUM; HTR-10 REACTOR; REGULATIONS; SAFETY; SIMULATION; TEMPERATURE RANGE 0400-1000 K
Descriptors DEC
ASIA; ELEMENTS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FLUIDS; GAS COOLED REACTORS; GASES; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; LAWS; NONMETALS; RARE GASES; REACTORS; RESEARCH AND TEST REACTORS; TEMPERATURE RANGE; TEST FACILITIES; TEST REACTORS

Optional Information

Notes
8 figs., 8 refs.