High Temperature Engineering Test Reactor (HTTR) Description

The High Temperature Engineering Test Reactor (HTTR) is a graphite moderated and helium cooled prismatic reactor developed and operated by the Japan Atomic Energy Agency (JAEA). It was designed to test the safety of high temperature gas cooled reactors (HTGRs). The HTTR is the first and only HTGR in Japan; it first reached criticality in 1998 and was used to conduct safety analyses and performance tests until 2011, when it was shut down following the Fukushima accident.

Figure 1: Drawing plan of the HTTR in built in Ibaraki, Japan, Masuro OGAWA (2007).

In 2021, following a safety review by the Nuclear Regulation Authority, the HTTR was restarted. As a part of a cooperative effort between Japan and the United States (U.S.) under the Civil Nuclear Energy Research and Development Working Group (CNWG), the Advanced Reactor Technologies (ART) program at Idaho National Laboratory (INL) and JAEA involves a multi-national research project sponsored by the Nuclear Energy Agency of the Organization of Economic Cooperation and Development Labouré et al. (2022) and Labouré et al. (2023).

The general radial layout of the HTTR core, shown in Figure 1, follows a hexagonal lattice containing 30 fuel columns, 16 control rods, 12 replaceable reflectors, and 3 instrumentation columns surrounded by a permanent reflector.

Figure 1: HTTR core layout with fuel (columns 1-4), control rods (C, R1, R2, R3), replaceable reflectors (RR), and instrumentation (I), from Laboure et al. (2018).

Each fuel column is composed of nine blocks: five fuel pins fitted between two top and two bottom axial reflectors, represented in Figure 2. Each block measures 58 cm in height. The burnable poison and fuel enrichment inside the fuel pins vary both radially and axially. Cold helium flows upwards between the permanent reflectors and the reactor pressure vessel (RPV), then flows downward through the cooling channels inside the core.

Figure 2: Description of the four different HTTR fuel columns (UO wt% fuel enrichment/burnable poison wt% enrichment), from Laboure et al. (2018).

The model described here assumes the reactor to be operating at 9MW. HTTR typically operates at 9 or 30 MW.

The general HTTR design specifications are summarized below in Table I, from Laboure et al. (2018).

Design SpecificationsValueUnit
Thermal Power9MW
Outlet Coolant Temperature320C
Inlet Coolant Temperature180C
Core StructureGraphite
Equivalent Core Diameter2.3m
Effective Core Height2.9m
Average Power Density2.5W/cm
Fuel/EnrichmentUO/3-10 wt%
Fuel TypePin in Block
Burnup Period660EFPD
Coolant Material/FlowHelium Gas/Downward
Reflector Thickness: Top/Slide/Bottom1.16/0.99/1.16m
Number of Fuel Assemblies150
Number of Fuel Columns30
Number of Control Rod Pairs: In Core/In Reflector7/9

The general HTTR fuel specifications are summarized below in Table II, from Laboure et al. (2018).

Fuel Kernel
MaterialUO
Diameter600 m
Density10.41 g/cm
Coated Fuel Particle
Type/MaterialTRISO
Diameter920 m
Impurity<3 (Boron Equivalent) ppm
Fuel Compact
TypeHollow Cylinder
MaterialCoated Fuel Particles, Binder, and Graphite
Outer/Inner Diameter2.6/1.0 cm
Length3.9 cm
Packing Fraction of CFPs30 vol%
Density of Graphite Matrix1.7g/cm
Impurity in Graphite Matrix<1.2 (Boron Equivalent) ppm
Fuel Rod
Outer Diameter3.4 cm
Sleeve Thickness3.75 mm
Length54.6 cm
Number of Fuel Compacts14
Number of Rods in a Block31/33
Graphite Sleeve
TypeCylinder
MaterialIG 110 Graphite
Length58 cm
Gap Width between Compact and Sleeve0.25 mm
Graphite Block
Type/ConfigurationPin in Block/Hexagonal
MaterialIG 110 Graphite
Width across Flats36 cm
Height58 cm
Fuel Hole Diameter4.1 cm
Density1.75 g/cm
Impurity<1 (Boron Equivalent) ppm

References

  1. Vincent M. Laboure, Javier Ortensi, and Andrew Hummel. HTTR 3 D Cross Section Generation with Serpent and MAMMOTH. Technical Report, Idaho National Laboratory, 2018. doi:10.2172/1484524.[BibTeX]
  2. Vincent Labouré, Javier Ortensi, Nicolas Martin, Paolo Balestra, Derek Gaston, Yinbin Miao, and Gerhard Strydom. Improved Multiphysics Model of the High Temperature Engineering Test Reactor for the Simulation of Loss-of-Forced-Cooling Experiments. Annals of Nuclear Energy, 189:109838, 2023.[BibTeX]
  3. Vincent M. Labouré, Matilda Anna Elisabeth Åberg Lindell, Javier Ortensi, Gerhard Strydom, and Paolo Balestra. FY22 Status Report on the ART-GCR CMVB and CNWG International Collaborations. Technical Report, Idaho National Laboratory, 2022. doi:10.2172/1893099.[BibTeX]
  4. Japan Atomic Energy Agency Masuro OGAWA. Overview of HTTR Project. 2007. Accessed: 2023-09-05. URL: https://www-pub.iaea.org/MTCD/Meetings/PDFplus/2007/cn152/cn152p/Overview%20of%20HTTR%20Project%20Ogawa.pdf.[BibTeX]