Published October 1997 | Version v1
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The assessment of variations in the MIGR reactor design parameters with decreasing nuclear fuel enrichment down to 20%

Creators

  • 1. Minatom of Russia, Moscow (Russian Federation)
  • 2. VNIITF, Snezhinsk (Russian Federation)
  • 3. RDIPE, Moscow (Russian Federation)
  • 4. RRC 'Kurchatov Institute', Moscow (Russian Federation)

Description

The variation of physical parameters in the MIGR reactor has been studied in the case of conversion from highly enriched (90%) fuel to low enriched (20%) one. Studies have shown that in the case of conversion to 20% enrichment, ∼1.5 times increase in uranium-235 loading will be required, uranium concentration in graphite will increase by ∼7 times that, however, will not result in restrictions for graphite impregnation by uranium (in the IGR reactor, uranium concentration in graphite is 3 g per 1 kg and in the MIGR reactor with fuel of 20% enrichment in U-235, it is not more than 4 g per 1 kq). (author)

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Part of:
Abstracts and papers of the 1997 International RERTR Meeting

Additional details

Identifiers

URL
http://www.td.anl.gov/Programs/RERTR/PAPERS97.html;

Publishing Information

Imprint Title
Abstracts and papers of the 1997 International RERTR Meeting
Imprint Pagination
259 p.
Journal Page Range
[1 p.]
Report number
INIS-XA-C--009

Conference

Title
20. international meeting on Reduced Enrichment for Research and Test Reactors (RERTR)
Dates
5-10 Oct 1997
Place
Jackson Hole, WY (United States)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
35089156
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONCENTRATION RATIO; GRAPHITE; GRAPHITE MODERATED REACTORS; HIGHLY ENRICHED URANIUM; IGR REACTOR; REACTOR CORES; SLIGHTLY ENRICHED URANIUM; URANIUM 235
Descriptors DEC
ACTINIDE NUCLEI; ACTINIDES; ALPHA DECAY RADIOISOTOPES; CARBON; ELEMENTS; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; EVEN-ODD NUCLEI; EXPERIMENTAL REACTORS; GRAPHITE MODERATED REACTORS; HEAVY NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; IRRADIATION REACTORS; ISOMERIC TRANSITION ISOTOPES; ISOTOPE ENRICHED MATERIALS; ISOTOPES; MATERIALS; MATERIALS TESTING REACTORS; METALS; MINERALS; MINUTES LIVING RADIOISOTOPES; NONMETALS; NUCLEI; PULSED REACTORS; RADIOISOTOPES; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SPONTANEOUS FISSION RADIOISOTOPES; TANK TYPE REACTORS; THERMAL REACTORS; URANIUM; URANIUM ISOTOPES; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES

Optional Information