Published 1977
| Version v1
Book
Neutron transport through straight and once bent sodium pipe in shielding of fast reactor
Creators
- 1. Nuclear Research Inst., Rez, Czechoslovakia
Description
The paper presents measurements and calculations on the neutron attenuation along 40 cm diameter straight and bent sodium pipe. The following types of spectrometers were used in measurements on VVR-S reactor: stilbene scintillator, proportional hydrogen counter, multisphere technique and activation foils. Discrete ordinates and Monte Carlo methods were used to study this type of problem
Additional details
Publishing Information
- Publisher
- Science Press.
- Imprint Place
- Princeton, NJ
- Imprint Title
- Reactor shielding
- Journal Page Range
- p. 246-252.
Conference
- Title
- National Transportation Safety Board meeting.
- Dates
- 24 Jan 1977.
- Place
- Washington, DC, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 9418815
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- LMFBR TYPE REACTORS; NEUTRON TRANSPORT; PIPES; RADIATION STREAMING; REACTOR COOLING SYSTEMS; SHIELDING
- Descriptors DEC
- BREEDER REACTORS; COOLING SYSTEMS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; REACTOR COMPONENTS; REACTORS
Optional Information
- Notes
- Imprint:See CONF-770104--.