Published 1978
| Version v1
Miscellaneous
Calculation of the thermal neutron spectrum in high-temperature gas-cooled graphite-moderated reactors
Creators
Description
Technique for solving the differential equation which describes the thermal neutron flux in the heavy gas model approximation are reported. The validity of using the heavy gas model for calculation of the thermal neutron spectrum in homogeneous water and absorber mixtures has been investigated. The results of calculating the thermal neutron spectrum in a spherical fuel element of a high-temperature gas reactor at various fuel burnups performed according to the TERMOS multigroup program are presented
Additional details
Additional titles
- Original title (Russian)
- Расчет спектра тепловых нейтронов в высокотемпературных газоохлаждаемых графитовых реакторах (VTGR)
Publishing Information
- Imprint Title
- Physics of nuclear reactors. No. 7
- Journal Page Range
- p. 54-59.
- Report number
- INIS-mf--6122
INIS
- Country of Publication
- USSR
- Country of Input or Organization
- USSR
- INIS RN
- 11566011
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ANALYTICAL SOLUTION; BURNUP; DIFFERENTIAL EQUATIONS; HTGR TYPE REACTORS; NEUTRON SPECTRA; THERMAL NEUTRONS
- Descriptors DEC
- BARYONS; ELEMENTARY PARTICLES; EQUATIONS; FERMIONS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HADRONS; NEUTRONS; NUCLEONS; REACTORS; SPECTRA
Optional Information
- Notes
- 5 refs.; 2 figs.; 1 table. Imprint:Fizika yadernykh reaktorov. Vypusk 7.