Published August 2010
| Version v1
Journal article
MC simulation of a PGNAA system for on-line cement analysis
- 1. State Key Laboratory of Geohazard Prevention and Geoenvironmental Protection, Chengdu University of Technology (China)
- 2. Nuclear Power Institute of China, Chengdu (China)
- 3. China Academy of Engineering Physics, Mianyang (China)
Description
A prompt gamma neutron activation analysis system with a 252Cf neutron source for on-line cement analysis has been simulated with the MCNP code. The results indicate that the optimum arrangement is a Bi shield of 20-mm thickness, a polyethylene moderator of 50-mm thickness, a source-to-sample distance of 70 mm, and cement samples of 1200 mm x 600 mm x 170 mm. To absorb thermal neutrons and suppress low-energy γ-rays, the optimum-sized sheets are 150 mm x 7 mm Cd, and 150 mm x 15 mm Pb. (authors)
Additional details
Publishing Information
- Journal Title
- Nuclear Science and Techniques
- Journal Volume
- 21
- Journal Issue
- 4
- Journal Page Range
- p. 221-226
- ISSN
- 1001-8042
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 45020991
- Subject category
- S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; S36: MATERIALS SCIENCE;
- Descriptors DEI
- CALIFORNIUM 252; CEMENTS; MODERATORS; NEUTRON ACTIVATION ANALYSIS; NEUTRON SOURCES; POLYETHYLENES; SHEETS; SHIELDS; SIMULATION; THERMAL NEUTRONS; THICKNESS
- Descriptors DEC
- ACTINIDE NUCLEI; ACTIVATION ANALYSIS; ALPHA DECAY RADIOISOTOPES; BARYONS; BUILDING MATERIALS; CALIFORNIUM ISOTOPES; CHEMICAL ANALYSIS; DIMENSIONS; ELEMENTARY PARTICLES; EVEN-EVEN NUCLEI; FERMIONS; HADRONS; HEAVY NUCLEI; ISOTOPES; MATERIALS; NEUTRONS; NONDESTRUCTIVE ANALYSIS; NUCLEI; NUCLEONS; ORGANIC COMPOUNDS; ORGANIC POLYMERS; PARTICLE SOURCES; POLYMERS; POLYOLEFINS; RADIATION SOURCES; RADIOISOTOPES; SPONTANEOUS FISSION RADIOISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 8 figs., 1 tabs., 10 refs.