Abstract. ORIGEN is a widely used computer code for calculating the buildup, decay, and processing o f radioactive materials. The ORIGEN code was created by famous and reputable nuclear institution in United States, Oak Ridge National Laboratory (ORNL). For a nuclear reactor, either it is a nuclear power reactor or nuclear research reactor, the radionuclide inventories data is important. This data is acquired by performing source term modelling. A fresh nuclear fuel could not cause any harm to human. However, used nuclear fuel could pose danger threat to human. The fission products particularly long-lived radionuclides i.e.H-3, Co-60, Cs-137 that are generated inside the fuel yield a significance amount o f radioactivity. Therefore, there i...
The ORIGEN-Z-1-11 in its basic calculating method is derived from the ORNL point depletion code ORIG...
Abstract. The known ORNL ORIGEN code is widely spread over the world for inventory, activity and dec...
Development of accurate and reliable methods to safeguard spent nuclear fuel residing in dry in-teri...
The Oak Ridge National Laboratory computer code, ORIGEN2.2 (CCC-371, 2002), was used to obtain the e...
The DKPRO code solves the general problem of modeling complex nuclear wastes streams using ORIGEN2 r...
Vol. 2, Rev. 6F7.iii ORIGEN-S computes time-dependent concentrations and source terms of a large num...
Nuclear materials contain a number of radionuclides produced from radioactive decay process. The com...
This paper is related to the Clearance Potential Index, Ingestion and Inhalation Hazard Factors of t...
The Tower is an official publication of the Georgia Tech Board of Student Publications and is sponso...
The estimation of core inventory and source term of nuclear reactor is a part of procedures for cond...
The estimation of core inventory and source term of nuclear reactor is a part of procedures for cond...
ORIGEN2 is a versatile point depletion and decay computer code for use in simulating nuclear fuel cy...
Due to high radioactivity and significant content of medium- and long-lived radionuclides, different...
This paper reviews the accuracy and precision of methods used by United States electric utilities to...
ORIGEN2 calculations were performed for TRIGA spent fuel elements from the Hanford Neutron Radiograp...
The ORIGEN-Z-1-11 in its basic calculating method is derived from the ORNL point depletion code ORIG...
Abstract. The known ORNL ORIGEN code is widely spread over the world for inventory, activity and dec...
Development of accurate and reliable methods to safeguard spent nuclear fuel residing in dry in-teri...
The Oak Ridge National Laboratory computer code, ORIGEN2.2 (CCC-371, 2002), was used to obtain the e...
The DKPRO code solves the general problem of modeling complex nuclear wastes streams using ORIGEN2 r...
Vol. 2, Rev. 6F7.iii ORIGEN-S computes time-dependent concentrations and source terms of a large num...
Nuclear materials contain a number of radionuclides produced from radioactive decay process. The com...
This paper is related to the Clearance Potential Index, Ingestion and Inhalation Hazard Factors of t...
The Tower is an official publication of the Georgia Tech Board of Student Publications and is sponso...
The estimation of core inventory and source term of nuclear reactor is a part of procedures for cond...
The estimation of core inventory and source term of nuclear reactor is a part of procedures for cond...
ORIGEN2 is a versatile point depletion and decay computer code for use in simulating nuclear fuel cy...
Due to high radioactivity and significant content of medium- and long-lived radionuclides, different...
This paper reviews the accuracy and precision of methods used by United States electric utilities to...
ORIGEN2 calculations were performed for TRIGA spent fuel elements from the Hanford Neutron Radiograp...
The ORIGEN-Z-1-11 in its basic calculating method is derived from the ORNL point depletion code ORIG...
Abstract. The known ORNL ORIGEN code is widely spread over the world for inventory, activity and dec...
Development of accurate and reliable methods to safeguard spent nuclear fuel residing in dry in-teri...