Published March 1962
| Version v1
Book
Nuclear data requirements for fast and intermediate reactor calculations
Description
During 1960/61, some work has been done at Karlsruhe in the compilation of reliable nuclear data for fast- and intermediate-reactor calculations. Materials included thus far are He, O16, Na23, Cr, Fe, Ni, Mo, U235, U238 and Pu239. For fast- and intermediate-reactor optimization studies, reliable theoretical prediction of space-dependent neutron energy spectra, critical masses, breeding ratios, burn-up, Doppler coefficients and related subjects, the author was interested in much more detailed microscopic cross-section data concerning mainly neutron absorption and fission than are needed, for example, for the evaluation of few-group constants in the conventional multi-group diffusion theory. In spite of much progress in the experimental determination and theoretical interpretation of nuclear data, many inconsistencies in the experimental results of different authors and laboratories and large gaps in experimental nuclear-data work still remain. This paper discusses a great number of these gaps and inconsistencies in respect of the above-mentioned nuclei. (author)
Abstract (French)
En 1960/61, des travaux ont ete executes a Karlsruhe en vue de reunir des donnees nucleaires sures pour les calculs de reacteurs a neutrons rapides et a neutrons intermediaires. Les matieres etudiees jusqu'a present sont: He, 16O, 23Na, Cr, Fe, Ni, Mo, 235U, 238U et 239Pu. Pour retablissement des conditions optima concernant les reacteurs a neutrons rapides et a neutrons intermediaires, pour calculer avec precision la distribution spatiale des flux de neutrons, les masses critiques, les taux de surgeneration, la combustion, les coefficients Doppler et les elements connexes, l'auteur avait besoin de donnees beaucoup plus detaillees sur les sections efficaces microscopiques - notamment en ce qui concerne l'absorption et la fission des neutrons - que, par exemple, pour l'evaluation des constantes fondees sur l'emploi de quelques groupes dans la theorie classique de la diffusion a plusieurs groupes. En depit de grands progres dans la determination experimentale et l'interpretation theorique des donnees nucleaires, on constate encore des contradictions dans les resultats des experiences de divers auteurs et laboratoires, et il existe toujours de graves lacunes dans les travaux sur les donnees nucleaires. L'auteur traite d'un grand nombre de ces lacunes et contradictions en ce qui concerne les elements mentionnes plus haut. (author)Abstract (Spanish)
En los anos 1960 y 1961 se ha estado trabajando en Karlsruhe en la compilacion de datos nucleares fidedignos que se utilizan en los calculos de reactores de neutrones rapidos e intermedios. Los elementos estudiados hasta el presente comprenden: He, 16O, 23Na, Cr, Fe, Ni, Mo, 235U, 238U y 239Pu. Para establecer los parametros optimos de los reactores rapidos e intermedios, y para poder predecir teoricamente con suficiente precision los espectros de las energias neutronicas en funcion del espacio, las masas criticas, las razones de reproduccion, el grado de combustion, los coeficientes Doppler, etc., se requieren datos mucho mas detallados sobre las secciones eficaces microscopicas -especialment e sobre la absorcion neu tronica y la fision- que, por ejemplo, para evaluar las constantes de algunos grupos en la teoria clasica de difusion de grupos multiples. A pesar de los notables progresos realizados en la determinacion experimental y en la interpretacion teorica de los datos nucleares, siguen existiendo todavia muchas discrepancias entre los resultados experimentales dados a conocer por distintos autores y laboratorios; asimismo, subsisten grandes lagunas en los datos nucleares. En la memoria se examina toda una serie de esas lagunas y contradicciones en relacion con los nuclidos mencionados mas arriba. (author)Abstract (Russian)
V techenie 1960/61 godov v Karlsrueh byla provedena nekotoraya rabota po kompilyatsii nadezhnykh yadernykh dannykh dlya raschetov reaktorov na bystrykh i promezhutochnykh nejtronakh. K materialam, kotorye poka voshli v kompilyatsiyu, otnosyatsya gelij, kislorod-16, natrij-23, khrom, zhelezo, nikel', molibden, uran-235, uran-238 i plutonij-239. Dlya osushchestvleniya uspeshnykh issledovanij reaktorov na bystrykh i promezhutochnykh nejtronakh, dlya nadezhnogo teoreticheskogo predskazaniya prostranstvenno j zavisimosti spektrov nejtronnoj ehnergii, kriticheskikh mass, koehffitsientov vosproizvodstva , vygoraniya, koehffitsientov Dopplera i otnosyashchikhsya k nim problem avtor dannogo doklada zainteresovan v poluchenii bolee podrobnykh dannykh o mikroskopicheski kh poperechnykh secheniyakh, kasayushchikhsya glavnym obrazom pogloshcheniya i deleniya nejtronov, chem trebuetsya, naprimer, dlya otsenki konstant nebol'shego kolichestva grupp v obychnoj mnogogruppovoj teorii diffuzii. Nesmotrya na znachitel'nyj progress v ehksperimental'no m opredelenii i teoreticheskom tolkovanii yadernykh dannykh, po-prezhnemu imeyut mesto mnogochislennye raskhozhdeniya v ehksperimental'nykh rezul'tatakh razlichnykh avtorov i laboratorij i bol'shie probely v ehksperimental'no j rabote po polucheniyu yadernykh dannykh. V nastoyashchem doklade rassmatrivaetsya tselyj ryad ehtikh probelov i raskhozhdenij, kasayushchikhsya yader vysheupomyanutykh materialov. (author)Additional details
Additional titles
- Original title (English)
- Constantes nucleaires requises pour les calculs de reacteurs a neutrons rapides et a neutrons intermediaires; Trebovaniya v otnoshenii yadernykh dannykh dlya raschetov reaktorov na bystrykh i promezhutochnykh nejtronakh; Datos nucleares necesarios para los calculos de reactores rapidos e intermedios
Publishing Information
- Publisher
- Globus, Druck- und Verlagsanstalt, Vienna
- Imprint Place
- Vienna (International Atomic Energy Agency (IAEA))
- Imprint Title
- Physics of Fast and Intermediate Reactors. V. I. Proceedings of the Seminar on the Physics of Fast and Intermediate Reactors. V. I
- Imprint Pagination
- 500 p.
- Series
- Proceedings Series
- Journal Page Range
- p. 3-20
- ISSN
- 0074-1884
Conference
- Title
- Seminar on Physics of Fast and Intermediate Reactors
- Dates
- 3-11 Aug 1961
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 44032428
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ABSORPTION; BREEDING RATIO; BURNUP; CHROMIUM; ENERGY SPECTRA; EVALUATED DATA; EXPERIMENTAL DATA; FAST REACTORS; FISSION; GROUP CONSTANTS; HELIUM; INTERMEDIATE REACTORS; IRON; MOLYBDENUM; MULTIGROUP THEORY; NEUTRON DIFFUSION EQUATION; NICKEL; OXYGEN 16; PLUTONIUM 239; SODIUM 23; TOTAL CROSS SECTIONS; URANIUM 235; URANIUM 238
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; CONVERSION RATIO; CROSS SECTIONS; DATA; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; DIMENSIONLESS NUMBERS; ELEMENTS; EPITHERMAL REACTORS; EQUATIONS; EVEN-EVEN NUCLEI; EVEN-ODD NUCLEI; FLUIDS; GASES; HEAVY NUCLEI; INFORMATION; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; LIGHT NUCLEI; METALS; MINUTES LIVING RADIOISOTOPES; NEUTRON TRANSPORT THEORY; NONMETALS; NUCLEAR REACTIONS; NUCLEI; NUMERICAL DATA; ODD-EVEN NUCLEI; OXYGEN ISOTOPES; PARTIAL DIFFERENTIAL EQUATIONS; PLUTONIUM ISOTOPES; RADIOISOTOPES; RARE GASES; REACTORS; REFRACTORY METALS; SODIUM ISOTOPES; SORPTION; SPECTRA; SPONTANEOUS FISSION RADIOISOTOPES; STABLE ISOTOPES; TRANSITION ELEMENTS; TRANSPORT THEORY; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 99 refs, 8 figs, 1 tab Imprint:In three volumes
- Secondary number(s)
- IAEA-SM--18/4