Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Delayed neutron spectra from individual short pulse (approx. 50 .mu.s) fission of small 235U samples (50 mg) were measured using a small (5 cm OD x 5 cm length) NE 213 neutron spectrometer. The irradiating fast neutron flux (approx. 1013 neutrons/cm2) for these measurements was provided by the Godiva fast burst reactor at the Los Alamos Critical Experiment Facility (LACEF). A high speed pneumatic transfer system was used to transfer the 50 mg 235U samples from the irradiation position near the Godiva assembly to a remote shielded counting room containing the NE 213 spectrometer and associated electronics. Data were acquired in sixty-four 0.5 s time bins and over an energy range 1 to 7 MeV. Comparisons between these measurements and a detailed model calculation performed at Los Alamos is presented.
Delayed Neutron Spectra from Short Pulse Fission of Uranium-235
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Delayed neutron spectra from individual short pulse (approx. 50 .mu.s) fission of small 235U samples (50 mg) were measured using a small (5 cm OD x 5 cm length) NE 213 neutron spectrometer. The irradiating fast neutron flux (approx. 1013 neutrons/cm2) for these measurements was provided by the Godiva fast burst reactor at the Los Alamos Critical Experiment Facility (LACEF). A high speed pneumatic transfer system was used to transfer the 50 mg 235U samples from the irradiation position near the Godiva assembly to a remote shielded counting room containing the NE 213 spectrometer and associated electronics. Data were acquired in sixty-four 0.5 s time bins and over an energy range 1 to 7 MeV. Comparisons between these measurements and a detailed model calculation performed at Los Alamos is presented.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Delayed neutron spectra from individual short pulse (approx. 50 .mu.s) fission of small 235U samples (50 mg) were measured using a small (5 cm OD x 5 cm length) NE 213 neutron spectrometer. The irradiating fast neutron flux (approx. 1013 neutrons/cm2) for these measurements was provided by the Godiva fast burst reactor at the Los Alamos Critical Experiment Facility (LACEF). A high speed pneumatic transfer system was used to transfer the 50 mg 235U samples from the irradiation position near the Godiva assembly to a remote shielded counting room containing the NE 213 spectrometer and associated electronics. Data were acquired in sixty-four 0.5 s time bins and over an energy range 1 to 7 MeV. Comparisons between these measurements and a detailed model calculation performed at Los Alamos is presented.
Delayed Neutrons from U235 After Short Irradiation
Measured Delayed Neutron Spectra from the Fission of U-235 and Np-237
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 3
Book Description
Texas A & M University, in collaboration with Oak Ridge National Laboratory / the Japan Atomic Energy Research Institute, have been actively studying the delayed neutron emission characteristics of the higher actinide isotopes for several years. 1-3 Recently, a proton recoil detector system was designed, built, and characterized for use in measuring delayed neutron energy spectra following neutron induced fission. The system has been used to measure aggregate delayed neutron energy spectra from neutron induced fission of U-235 and Np-237. These spectra have also been compared to that calculated using individual precursor P, values, yields, and spectra from the ENDF/B-VI file. A proton recoil detector array consisting of three LND Model 28305 high- -pressure proton recoil detectors has been constructed at the Texas A & M University Nuclear Science Center. The array was characterized using several neutron and gamma- ray sources to check for efficiency, gamma-ray response, and reliability of the unfolding techniques. Resultant measured proton recoil distributions were unfolded using a modified version of the spectrum unfolding code PSNS (the new code was renamed SAC). SAC used response functions calculated using MCNP 4A. This feature allowed the inclusion of several inches of lead between the detector and the source to decrease the detector's sensitivity to gamma-rays, while appropriately accounting for the effect on the transmitted neutron spectrum. Following proper calibration of the array, highly-purified sources of U-235 were irradiated in the Nuclear Science Center Reactor (NSCR) at a power of 1 MW for 200.
Publisher:
ISBN:
Category :
Languages : en
Pages : 3
Book Description
Texas A & M University, in collaboration with Oak Ridge National Laboratory / the Japan Atomic Energy Research Institute, have been actively studying the delayed neutron emission characteristics of the higher actinide isotopes for several years. 1-3 Recently, a proton recoil detector system was designed, built, and characterized for use in measuring delayed neutron energy spectra following neutron induced fission. The system has been used to measure aggregate delayed neutron energy spectra from neutron induced fission of U-235 and Np-237. These spectra have also been compared to that calculated using individual precursor P, values, yields, and spectra from the ENDF/B-VI file. A proton recoil detector array consisting of three LND Model 28305 high- -pressure proton recoil detectors has been constructed at the Texas A & M University Nuclear Science Center. The array was characterized using several neutron and gamma- ray sources to check for efficiency, gamma-ray response, and reliability of the unfolding techniques. Resultant measured proton recoil distributions were unfolded using a modified version of the spectrum unfolding code PSNS (the new code was renamed SAC). SAC used response functions calculated using MCNP 4A. This feature allowed the inclusion of several inches of lead between the detector and the source to decrease the detector's sensitivity to gamma-rays, while appropriately accounting for the effect on the transmitted neutron spectrum. Following proper calibration of the array, highly-purified sources of U-235 were irradiated in the Nuclear Science Center Reactor (NSCR) at a power of 1 MW for 200.
Dependence of Delayed-neutron Energy Spectra on the Energy of Neutrons which Induce Fission of U-235
Author: Quazi Sharfuddin
Publisher:
ISBN:
Category : Delayed neutrons
Languages : en
Pages : 202
Book Description
Publisher:
ISBN:
Category : Delayed neutrons
Languages : en
Pages : 202
Book Description
Delayed Neutrons from Fissionable Isotopes of Uranium, Plutonium, and Thorium
Author: George Robert Keepin
Publisher:
ISBN:
Category : Delayed neutrons
Languages : en
Pages : 58
Book Description
Publisher:
ISBN:
Category : Delayed neutrons
Languages : en
Pages : 58
Book Description
Energies of the Delayed Neutrons from U235 Fission Products
An Investigation of the Delayed Neutron Decay Curves Resulting from Uranium and Plutonium Fission
Author: C. Redman
Publisher:
ISBN:
Category : Delayed neutrons
Languages : en
Pages : 20
Book Description
Publisher:
ISBN:
Category : Delayed neutrons
Languages : en
Pages : 20
Book Description
Delayed Fission Neutrons
Author: International Atomic Energy Agency
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 268
Book Description
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 268
Book Description
Delayed-neutron Energy Spectra for Thermal Fisson of U-235
Author: Robert Steven Tanczyn
Publisher:
ISBN:
Category : Delayed neutrons
Languages : en
Pages : 302
Book Description
Publisher:
ISBN:
Category : Delayed neutrons
Languages : en
Pages : 302
Book Description