Author: Yong Chen
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The delayed neutron emission rates of U-235 and Pu-239 samples were measured accurately from a thermal fission reaction. A Monte Carlo calculation using the Geant4 code was used to demonstrate the neutron energy independence of the detector used in the counting station. A set of highly purified actinide samples (U-235 and Pu-239) was irradiated in these experiments by using the Texas A & M University Nuclear Science Center Reactor. A fast pneumatic transfer system, an integrated computer control system, and a graphite-moderated counting system were constructed to perform all these experiments. The calculated values for the five-group U-235 delayed neutron parameters and the six-group Pu-239 delayed neutron parameters were compared with the values recommended by Keepin et al. (1957) and Waldo et al. (1981). These new values differ slightly from literature values. The graphite-moderated counting station and the computerized pneumatic system are now operational for further delayed neutron measurement.
Delayed Neutron Emission Measurements for U-235 and Pu-239
Author: Yong Chen
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The delayed neutron emission rates of U-235 and Pu-239 samples were measured accurately from a thermal fission reaction. A Monte Carlo calculation using the Geant4 code was used to demonstrate the neutron energy independence of the detector used in the counting station. A set of highly purified actinide samples (U-235 and Pu-239) was irradiated in these experiments by using the Texas A & M University Nuclear Science Center Reactor. A fast pneumatic transfer system, an integrated computer control system, and a graphite-moderated counting system were constructed to perform all these experiments. The calculated values for the five-group U-235 delayed neutron parameters and the six-group Pu-239 delayed neutron parameters were compared with the values recommended by Keepin et al. (1957) and Waldo et al. (1981). These new values differ slightly from literature values. The graphite-moderated counting station and the computerized pneumatic system are now operational for further delayed neutron measurement.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The delayed neutron emission rates of U-235 and Pu-239 samples were measured accurately from a thermal fission reaction. A Monte Carlo calculation using the Geant4 code was used to demonstrate the neutron energy independence of the detector used in the counting station. A set of highly purified actinide samples (U-235 and Pu-239) was irradiated in these experiments by using the Texas A & M University Nuclear Science Center Reactor. A fast pneumatic transfer system, an integrated computer control system, and a graphite-moderated counting system were constructed to perform all these experiments. The calculated values for the five-group U-235 delayed neutron parameters and the six-group Pu-239 delayed neutron parameters were compared with the values recommended by Keepin et al. (1957) and Waldo et al. (1981). These new values differ slightly from literature values. The graphite-moderated counting station and the computerized pneumatic system are now operational for further delayed neutron measurement.
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
Grande exposition de photographies à l'occasion du 800ème anniversaire de Tramelan
Delayed Neutrons from U235 After Short Irradiation
Measurements of Delayed Neutron Emission from Np-237, Am-241, and Am-243
Author: Habeeb H. Saleh
Publisher:
ISBN:
Category : Plutonium
Languages : en
Pages : 5
Book Description
Publisher:
ISBN:
Category : Plutonium
Languages : en
Pages : 5
Book Description
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
Neutron Emission from U-233, U-235, and Pu-239 Fission Fragments
Delayed Neutron Equilibrium Spectra of U-235, U-238, and Pu-239
Author: Eric S. Jacobs
Publisher:
ISBN:
Category : Uranium
Languages : en
Pages : 394
Book Description
Publisher:
ISBN:
Category : Uranium
Languages : en
Pages : 394
Book Description
Delayed Neutrons
Author: George Robert Keepin
Publisher:
ISBN:
Category : Delayed neutrons
Languages : en
Pages : 56
Book Description
A comprehensive review is given of existing measurements as of October 1955 on the properties of delayed neutrons from various fissionable isotopes. The relation of these measurements to current theory and practice is discussed.
Publisher:
ISBN:
Category : Delayed neutrons
Languages : en
Pages : 56
Book Description
A comprehensive review is given of existing measurements as of October 1955 on the properties of delayed neutrons from various fissionable isotopes. The relation of these measurements to current theory and practice is discussed.
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.