Development of SCINFUL-CG code to calculate response function of hybrid neutron detectors using scintillators
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Description
A computer code, SCINFUL-CG, has been developed to calculate the response functions of a hybrid scintillation detector for neutrons. SCINFUL is a code used to calculate the response function of organic scintillator in simple geometry for neutrons of 0.1 to 80 MeV. To expand the capability of this code, development of SCINFUL-CG was performed by introducing the geometry package MARS-CG, and the neutron transport cross-section data of silicon, oxygen and aluminum taken from the LA150 library. Validity of SCINFUL-CG was confirmed by comparing the calculated results with those by SCINFUL and MCNP-4B, and with the response functions measured in some neutron fields. From the results, it was concluded that SCINFUL-CG can be used for calculating the response functions and neutron spectra for the hybrid neutron detector. (author)
Availability note (English)
Available from the Internet at URL https://doi.org/10.1080/00223131.2002.10875194Additional details
Identifiers
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of the international conference on nuclear data for science and technology
- Imprint Pagination
- 1547 p.
- Journal Page Range
- p. 693-696
Conference
- Title
- International conference on nuclear data for science and technology
- Acronym
- ND 2001
- Dates
- 7-12 Oct 2001
- Place
- Tsukuba, Ibaraki (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 51063276
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALUMINIUM; CROSS SECTIONS; EV RANGE; KEV RANGE; MEV RANGE; NEUTRON DETECTORS; NEUTRON SPECTRA; NEUTRON TRANSPORT; OXYGEN; RESPONSE FUNCTIONS; S CODES; SCINTILLATION COUNTERS; SILICON
- Descriptors DEC
- COMPUTER CODES; ELEMENTS; ENERGY RANGE; FUNCTIONS; MEASURING INSTRUMENTS; METALS; NEUTRAL-PARTICLE TRANSPORT; NONMETALS; RADIATION DETECTORS; RADIATION TRANSPORT; SEMIMETALS; SPECTRA
Optional Information
- Notes
- 10 refs., 5 figs.; This record replaces 34024825 Imprint:Published as supplement 2 of Journal of Nuclear Science and Technology in 2 volumes