Nuclear data requirements for thermal reactor design and operation
Creators
- 1. Atomic Energy Establishment Winfrith, Dorchester, Dorset (United Kingdom)
Description
The accuracy required in calculations of the properties of thermal reactors, in all stages from initial assessment to final operation, is a matter of judgement. The factors to be considered in making this judgement are outlined, and it is suggested that a common basis of accuracy requirements for reactor properties be used. Even if this common basis for properties, such as reactivity, is assumed, there are many ways of meeting the desired objectives for a particular reactor system, ranging from large-scale experiments on a range of lattices to a more theoretical approach relying on sophisticated methods of calculation and accurate nuclear data. Nuclear data requirements should be determined on the basis of the latter approach. A variety of thermal reactors must be considered in arriving at the required accuracy of nuclear data, because materials differ from one reactor system to another, and even for the most common fissile isotopes, such as 235U and 239Pu, the concentrations and neutron spectrum will vary over a wide range. Finally, there are many ways in which the errors in nuclear data may be compounded, but the accuracy requirements at different neutron energies may be arranged to be consistent with the known difficulties of cross-section measurements at different energies. The nuclear data needs for thermal reactors are on the way to being met. The status of available data is briefly reviewed in the light of required accuracies, and outstanding requirements are considered, bearing in mind the contribution which integral measurements can make. (author)
Additional details
Publishing Information
- Publisher
- IAEA
- Imprint Place
- Vienna (Austria)
- Imprint Title
- Nuclear data for reactors. Proceedings of a conference on nuclear data - microscopic cross-sections and other data basic for reactors. V. 1
- Imprint Pagination
- 594 p.
- Series
- Proceedings series
- Journal Page Range
- p. 13-26
- ISSN
- 0074-1884
Conference
- Title
- Conference on nuclear data - microscopic cross-sections and other data basic for reactors
- Dates
- 17-21 Oct 1966
- Place
- Paris (France)
INIS
- Country of Publication
- Austria
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 41011334
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CROSS SECTIONS; ERRORS; NEUTRON SPECTRA; NUCLEAR DATA COLLECTIONS; PLUTONIUM 239; REACTIVITY; THERMAL REACTORS; URANIUM 235
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; EVEN-ODD NUCLEI; HEAVY NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MINUTES LIVING RADIOISOTOPES; NUCLEI; PLUTONIUM ISOTOPES; RADIOISOTOPES; REACTORS; SPECTRA; SPONTANEOUS FISSION RADIOISOTOPES; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 10 refs, 2 figs, 1 tab Imprint:Published in two volumes
- Secondary number(s)
- IAEA-CN--23/117