Published 1977
| Version v1
Report
Neutron dosimetry and spectral measurements at the White Sands Missile Range fast burst reactor
Description
The neutron dosimetry techniques and results from neutron spectral measurements of the White Sands Missile Range Fast Burst Reactor are reported. Characteristics of the neutron spectrum have been studied over the past several years as a result of measurements utilizing activation detector methods. The neutron output characteristics of the Fast Burst Reactor take the form of spectral measurements of free-field conditions, spectral measurements of perturbed environments and spectral parameters useful in describing test conditions
Additional details
Publishing Information
- Imprint Title
- Dosimetry methods for fuels, cladding, and structural materials
- Journal Page Range
- p. 683-698.
- Report number
- NUREG/CP--0004(Vol.2)
Conference
- Title
- dosimetry methods for fuels, cladding and structural materials.
- Acronym
- 2. ASTM-EURATOM symposium on reactor dosimetry
- Dates
- 2 - 7 Oct 1977.
- Place
- Palo Alto, CA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10441891
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACTIVATION DETECTORS; FBRF REACTOR; MEASURING METHODS; NEUTRON DOSIMETRY; NEUTRON SPECTRA
- Descriptors DEC
- DOSIMETRY; EPITHERMAL REACTORS; FAST REACTORS; MEASURING INSTRUMENTS; NEUTRON DETECTORS; PULSED REACTORS; RADIATION DETECTORS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SPECTRA