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Author Forsbacka, M.

Title Maximum temperature calculation and operational characteristics of fuel follower control rods for the AFRRI TRIGA reactor facility [electronic resource] / M. Forsbacka, M. Moore.

Imprint Bethesda, Md. : Defense Nuclear Agency, Armed Forces Radiobiology Research Institute, [1991]

Copies

Location Call No. OPAC Message Status
 Axe Federal Documents Online  D 15.12/2:91-1    ---  Available
Description 1 online resource (iii, 17 p.) : ill.
Series AFRRI ; TR91-1
AFRRI technical report ; TR 91-1.
Type Of Report Final report.
Note Title from title screen (viewed on Mar. 12, 2012).
"May 1991"--Technical rept. documentation p.
Bibliography Includes bibliographical references (p. 9-10).
Summary Operational requirements of the Armed Forces Radiobiology Research Institute (AFRRI) TRIGA reactor necessitate the implementation of fuel follower control rods (FFCR's). This technical report discusses the operational and safety aspects of FFCR installation. Thermal hydraulic analysis shows that FFCR's can be operated safely in the AFRRI TRIGA reactor. The maximum calculated fuel temperature at the maximum steady-state power level is well within the limit of the maximum safe operating temperature set by the Technical Specifications.
Funding NWED QAXM.
Subject Nuclear fuel rods -- Safety measures.
Radiation -- Safety measures.
Nuclear fission reactors(non-power)
Fission reactor physics.
Requirements.
Steady state.
Temperature.
Computations.
Radiobiology.
Fuels.
Military research.
Safety.
Operation.
Power levels.
Specifications.
Indexed Term NUCLEAR ENGINEERING
CONTROL RODS
TRIGA REACTOR
Added Author Moore, M.
Armed Forces Radiobiology Research Institute (U.S.)
Other Form: Microform: Forsbacka, M. Maximum temperature calculation and operational characteristics of fuel follower control rods for the AFRRI TRIGA reactor facility (OCoLC)27950904
Standard No. DTICE ADA237744
Gpo Item No. 0379-B-10 (online)
Sudoc No. D 15.12/2:91-1

 
    
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