A measurement of the effective delayed neutron fraction for TTR-1
Creators
- 1. Nippon Atomic Industry Group Co., Ltd., Kawasaki, Kanagawa (Japan)
- 2. Tokyo Shibaura Electric Co., Ltd., Central Research Laboratory, Kawasaki, Kanagawa (Japan)
Description
The effective delayed neutron fraction of TTR-1 has been measured by the substitution technique. The poison plates were made of boron steel. The changes in reactivity produced by the substitution of a poison plate for a fuel plate were measured by means of a calibrated control blade. The sum of the reactivity changes associated with the substitution of all the fuel plates of reactor was Σiρi = 136.6 $. The correction for the mismatch between the absorption cross-section of fuel and poison was made by using a 3 group diffusion equation. The group constant and the fuel cross-section were obtained by codes MUFT and TEMPEST. The reactivity change due to the absorption cross-section mismatch was obtained by the perturbation calculation. The result was Reactivity change due to absorption cross-section mismatch = 0.0622. >From this value and from the result of measurements, the value of the effective delayed neutron fraction is given by βeff = 1+0.0622/136.6-1.2 = 0.00784 (author)
Additional details
Additional titles
- Original title (Japanese)
- 東芝教育訓練用原子炉(TTR-1)の実効遅発中性子割合の測定
Identifiers
- DOI
- 10.3327/jaesj.6.7;
Publishing Information
- Journal Title
- Nippon Genshiryoku Gakkai-Shi
- Journal Volume
- 6
- Journal Issue
- 1
- Series
- 雑誌名:日本原子力学会誌
- Journal Page Range
- p. 7-15
- ISSN
- 0004-7120
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 55020868
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CRITICALITY; DELAYED NEUTRON FRACTION; DIFFUSION EQUATIONS; FISSION NEUTRONS; M CODES; MULTIGROUP THEORY; NEUTRON ABSORBERS; NEUTRON FLUX; REACTIVITY; T CODES; TOSHIBA REACTOR; URANIUM 235
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; BARYONS; COMPUTER CODES; DIFFERENTIAL EQUATIONS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; EQUATIONS; EVEN-ODD NUCLEI; FERMIONS; HADRONS; HEAVY NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MINUTES LIVING RADIOISOTOPES; NEUTRON TRANSPORT THEORY; NEUTRONS; NUCLEI; NUCLEONS; PARTIAL DIFFERENTIAL EQUATIONS; POOL TYPE REACTORS; RADIATION FLUX; RADIOISOTOPES; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SPONTANEOUS FISSION RADIOISOTOPES; THERMAL REACTORS; TRAINING REACTORS; TRANSPORT THEORY; URANIUM ISOTOPES; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 5 refs., 4 figs., 6 tabs.