Published October 1, 1976
| Version v1
Miscellaneous
CARNAC, Neutron Flux and Neutron Spectra in Criticality Accident
Creators
- 1. Departement de Surete Nucleaire, Commissariat a l'Energie Atomique (France)
Description
Nature of physical problem solved: Calculation of flux and neutron spectra in the case of a criticality accident. The method is unsophisticated but fast. The program is divided into two parts: (1) The code CRITIC is based on the Fermi age equation and evaluates the neutron number per fission emitted from a moderate critical system and its energy spectrum. (2) The code NARCISSE uses concrete current albedo, evaluates the product of neutron reflection on walls of the source containment and calculates the resulting flux at any point, and its energy distribution into 21 groups. The results obtained seem satisfactory, if compared with a Monte Carlo program
Availability note (English)
Available on-line: http://www.nea.fr/abs/html/nea-0393.htmlAdditional details
Identifiers
Publishing Information
- Imprint Pagination
- [html]
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 40085976
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Computer Program Description, Non-conventional Literature
- Descriptors DEI
- ALBEDO; C CODES; COMPUTER PROGRAM DOCUMENTATION; COMPUTERIZED SIMULATION; CONCRETES; CONTAINMENT; CRITICALITY; ENERGY SPECTRA; EQUATIONS; FERMI AGE THEORY; FISSION; MONTE CARLO METHOD; NEUTRON AGE; NEUTRON FLUX; NEUTRON SPECTRA; NEUTRONS; RADIATION ACCIDENTS; REACTOR ACCIDENT SIMULATION; REACTOR SAFETY; WEBSITES
- Descriptors DEC
- ACCIDENTS; BARYONS; BUILDING MATERIALS; CALCULATION METHODS; COMPUTER CODES; DOCUMENT TYPES; ELEMENTARY PARTICLES; FERMIONS; HADRONS; MATERIALS; NEUTRON SLOWING-DOWN THEORY; NUCLEAR REACTIONS; NUCLEONS; RADIATION FLUX; SAFETY; SIMULATION; SPECTRA
Optional Information
- Notes
- 3 refs.