Uranium‐233 fission detectors for neutron flux measurement in reactors

Autor:	K. R. Prasad, V. Balagi
Rok vydání:	1996
Předmět:	Materials science Fission Neutron flux Uranium-233 Nuclear engineering Detector Neutron detection Pulse mode Instrumentation
Zdroj:	Review of Scientific Instruments. 67:2197-2201
ISSN:	1089-7623 0034-6748
DOI:	10.1063/1.1147036
Popis:	Fission counters have been developed indigenously, using 233U as a sensing material for reactor startup applications. The first model has a counting sensitivity of 0.003 cps/nv in the pulse mode, 1×10−15 A/nv in the dc mode, and 6.4×10−29 A2 Hz/nv in the Campbell mode. A more sensitive counter with about 75 mg of 233U showed an average sensitivity of 0.02 cps/nv. A proposal for 233U in‐core miniature dc fission chambers is discussed. A design for high sensitivity (0.5 cps/nv) U‐233 pulse counter with transmission line‐type readout is also proposed.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::7107f2f5043051bc4983f64e2cb59346 https://doi.org/10.1063/1.1147036 Zobrazit plný text záznamu