Measurements of fission spectrum averaged cross sections for the 93Nb(eta,eta')93mNb reaction
Creators
- 1. Illinois Univ., Urbana, IL (USA)
- 2. Arkansas Univ., Fayetteville, AR (USA)
- 3. National Bureau of Standards, Gaithersburg, MD (USA)
- 4. INEL, EG and G, Idaho Falls, ID (USA)
Description
The spectrum averaged cross sections of the 93Nb(eta,eta')93mNb reaction in two standard fission neutron spectra have been measured by the activation method. The two standard spectra were the 252Cf spontaneous fission neutron spectrum and the thermal neutron induced fission neutron spectrum of 235U. Effective free-field neutron fluences were established by neutron source strength calibration against the National Standard Ra-Be source, fluence transfer from intermediate standard sources, and Monte Carlo scattering corrections. Activity measurements were performed by X-ray counting using a variety of Ge and Si(Li) spectrometers with sources prepared by deposition of niobium fluoride on analytical paper discs. The recommended values of the spectrum averaged cross sections for the 252Cf and 235U fission neutron spectra are, respectively, 150.6 mb +- 3% and 146.4 mb +- 3%
Additional details
Publishing Information
- Publisher
- ASTM.
- Imprint Place
- Philadelphia, PA (USA)
- ISBN
- 0-8031-1184-3
- Imprint Title
- Reactor dosimetry
- Imprint Pagination
- 798 p.
- Series
- STP 1001.
- Journal Page Range
- p. 235-244.
Conference
- Title
- methods, applications, and standardization.
- Acronym
- 6. ASTM-Euratom symposium on reactor dosimetry
- Dates
- 31 May - 5 Jun 1987.
- Place
- Jackson Hole, WY (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21022629
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACTIVATION ANALYSIS; BERYLLIUM; CALIBRATION; CALIFORNIUM 252 TARGET; CROSS SECTIONS; FISSION SPECTRA; LI-DRIFTED GE DETECTORS; LI-DRIFTED SI DETECTORS; MONTE CARLO METHOD; NEUTRON REACTIONS; NEUTRON SPECTRA; NIOBIUM FLUORIDES; NIOBIUM 93 REACTIONS; RADIATION SOURCES; RADIUM; REACTOR SAFETY EXPERIMENTS; SCINTILLATION COUNTERS; URANIUM 235 TARGET
- Descriptors DEC
- ALKALINE EARTH METALS; BARYON REACTIONS; CHEMICAL ANALYSIS; ELEMENTS; FLUORIDES; FLUORINE COMPOUNDS; GE SEMICONDUCTOR DETECTORS; HADRON REACTIONS; HALIDES; HALOGEN COMPOUNDS; HEAVY ION REACTIONS; LI-DRIFTED DETECTORS; MEASURING INSTRUMENTS; METALS; NIOBIUM COMPOUNDS; NONDESTRUCTIVE ANALYSIS; NUCLEAR REACTIONS; NUCLEON REACTIONS; RADIATION DETECTORS; SEMICONDUCTOR DETECTORS; SI SEMICONDUCTOR DETECTORS; SPECTRA; TARGETS; TRANSITION ELEMENT COMPOUNDS
Optional Information
- Secondary number(s)
- CONF-870501--.