Deterministic calculation of the effective delayed neutron fraction without using the adjoint neutron flux - 299
Creators
- 1. Argonne National Laboratory, Argonne, IL (United States)
- 2. Joint Institute for Power and Nuclear Research-Sosny, Minsk (Belarus)
Description
In 1997, Bretscher calculated the effective delayed neutron fraction by the k-ratio method. The Bretscher's approach is based on calculating the multiplication factor of a nuclear reactor core with and without the contribution of delayed neutrons. The multiplication factor set by the delayed neutrons (the delayed multiplication factor) is obtained as the difference between the total and the prompt multiplication factors. Bretscher evaluated the effective delayed neutron fraction as the ratio between the delayed and total multiplication factors (therefore the method is often referred to as k-ratio method). In the present work, the k-ratio method is applied by deterministic nuclear codes. The ENDF/B nuclear data library of the fuel isotopes (238U and 238U) have been processed by the NJOY code with and without the delayed neutron data to prepare multigroup WIMSD nuclear data libraries for the DRAGON code. The DRAGON code has been used for preparing the PARTISN macroscopic cross sections. This calculation methodology has been applied to the YALINA-Thermal assembly of Belarus. The assembly has been modeled and analyzed using PARTISN code with 69 energy groups and 60 different material zones. The deterministic and Monte Carlo results for the effective delayed neutron fraction obtained by the k-ratio method agree very well. The results also agree with the values obtained by using the adjoint flux. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, Illinois (United States)
- ISBN
- 978-0-89448-079-9
- Imprint Pagination
- 10 p.
Conference
- Title
- International Conference on Advances in Reactor physics to Power the Nuclear Renaissance
- Acronym
- PHYSOR 2010
- Dates
- 9-14 May 2010
- Place
- Pittsburgh, PA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 42107414
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ADJOINT FLUX; CROSS SECTIONS; DELAYED NEUTRON FRACTION; DELAYED NEUTRONS; MONTE CARLO METHOD; MULTIPLICATION FACTORS; NEUTRON TRANSPORT; NUCLEAR DATA COLLECTIONS; REACTOR CORES; THERMAL REACTORS; URANIUM 238; W CODES
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; BARYONS; CALCULATION METHODS; COMPUTER CODES; DIMENSIONLESS NUMBERS; ELEMENTARY PARTICLES; EVEN-EVEN NUCLEI; FERMIONS; FISSION NEUTRONS; HADRONS; HEAVY NUCLEI; ISOTOPES; NEUTRAL-PARTICLE TRANSPORT; NEUTRON FLUX; NEUTRONS; NUCLEI; NUCLEONS; RADIATION FLUX; RADIATION TRANSPORT; RADIOISOTOPES; REACTOR COMPONENTS; REACTORS; SPONTANEOUS FISSION RADIOISOTOPES; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 22 refs.