Published January 1990 | Version v1
Report Open

The conceptual design of High Temperature Engineering Test Reactor upgraded through utilizing Pebble-in-Block fuel (UHTTR)

Creators

  • 1. Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment

Description

This report presents the conceptual design study of future High Temperature Engineering Test Reactor upgraded through utilizing Pebble-in-Block fuel (UHTTR). The Pebble-in-Block fuel consists of a graphite basket and many spherical fuels. It is evident from this study that the average fuel burnup, average power density and max. fast neutron flux (E>0.18 MeV) of UHTTR can be increased through utilizing Pebble-in-Block fuel. The achievable average fuel burnup, average power density and max. fast neutron flux are 97 GWd/t, 7.2 W/cm and 6.7 x 1013 n/cm2/sec, respectively. (author)

Availability note (English)

MF available from INIS under the Report Number.

Files

21054205.pdf

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Additional details

Publishing Information

Imprint Pagination
78 p.
Report number
JAERI-M--89-222

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
21054205
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BURNABLE POISONS; BURNUP; COATED FUEL PARTICLES; FAST NEUTRONS; FUEL ELEMENTS; FUEL INTEGRITY; HTTR REACTOR; HYDRAULICS; POWER DENSITY; REACTOR CORES; SPECIFICATIONS; THERMAL STRESSES; THERMODYNAMICS
Descriptors DEC
BARYONS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FERMIONS; FUEL PARTICLES; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HADRONS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MATERIALS; NEUTRON ABSORBERS; NEUTRONS; NUCLEAR POISONS; NUCLEONS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; STRESSES