Published July 2015 | Version v1
Journal article

Comparative study on HTGR designs for passive decay heat removal

  • 1. Department of Nuclear Engineering, Tokyo Institute of Technology, 2-12-1-N1-19, Ookayama, Meguro-ku, Tokyo 152-8550 (Japan)
  • 2. Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, 2-12-1-N1-19, Ookayama, Meguro-ku, Tokyo 152-8550 (Japan)

Description

Highlights: •The sensitivity of peak temperatures does not depend on the reactor location. •Reactor design parameters' relationships for safe core are the same for two reactors. •The major parameter for practical-size above-ground RB is a core temperature. •Reactor power is the most influential factor for a reasonable-size underground RB. -- Abstract: The design parameters of a small high-temperature gas-cooled reactor (HTGR) for passive decay heat removal and located either above-ground or underground have been studied in previous works. In the present work, sensitivity analyses on peak temperatures of both the core and reactor building (RB) after reactor shutdown was conducted for both situations. It was found that the sensitivity of peak temperatures was quite similar for the two situations of the reactor, i.e., above- and below-ground. Therefore, a parametric survey on design parameters for long-life small prismatic HTGRs having features for successful decay heat removal using fundamental heat transfer mechanisms was performed for both reactor concepts. Comparison of the two conditions showed that a passively safe, low-power, underground reactor operating at high initial core temperature could have a practical size of RB. Conversely, for the RB size of an above-ground reactor with passive safety features to be reasonable, it could operate at relatively high power but would need a low initial core temperature. The appropriate sizes of reactor core and RB were evaluated for reactors with powers of 50 MWth, 100 MWth and 300 MWth having different maximum power densities and operating at temperatures of 1123 K, 973 K, and 573 K.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.pnucene.2014.07.013

Additional details

Identifiers

DOI
10.1016/j.pnucene.2014.07.013;
PII
S0149197014001942;

Publishing Information

Journal Title
Progress in Nuclear Energy
Journal Volume
82
Series
Innovative Nuclear Science and Technology Post Fukushima
Journal Page Range
p. 37-45
ISSN
0149-1970

Conference

Title
4. International Symposium on Innovative Nuclear Energy Systems
Acronym
INES-4
Dates
6-8 Nov 2013
Place
Tokyo (Japan)

INIS

Country of Publication
United Kingdom
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
51027496
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AFTER-HEAT REMOVAL; HEAT TRANSFER; HTGR TYPE REACTORS; PEAKS; REACTOR CORES; REACTOR DESIGN; REACTOR SHUTDOWN; SENSITIVITY ANALYSIS
Descriptors DEC
DESIGN; ENERGY TRANSFER; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; REACTOR COMPONENTS; REACTOR LIFE CYCLE; REACTORS; REMOVAL; SHUTDOWN

Optional Information

Notes
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