This report lists 42-group, coupled, neutron -gamma cross sections for H, D, T, /sup 3/He, /sup 4/He, /sup 6/Li, /sup 7/Li, Be, /sup 10/B, /sup 11/B, C, N, O, Na, Mg, Ai, Si, Cl, A, K, Ca, Fe, Cu, W, Pb, /sup 235/U, /sup 238/U, / sup 239/Pu, and /sup 240/Pu. Most of these materials are used in nuclear- weaponseffects calculations, where the elements for air, ground, and sea water are needed. Further, lists are given of cross sections for materials used in nuclear weapons vulnerability calculations, such as the elements of high explosives as well as materials that will undergo fusion and fission. Most of the common reactor materials are also listed. The 42 coupled neutron-gamma groups are split into 30 neutron groups (17 MeV through 1.39 x 1...
"For the U.S. Army Chemical Corps Nuclear Defense Laboratory"--Fore."Contract no.: DA-18-108-405-CML...
The original ANSL-V cross-section libraries (ORNL-6618) were developed over a period of several year...
The multi-group cross-section generation capability for neutrons is implemented in the FRENDY nuclea...
Multigroup cross-section covariance matrices are presented for fission in /sup 235/U, /sup 238/U, /s...
A nuclear data library was created for medium-energy-neutron-transport calculations. The 60-group li...
Evaluations are being done for the H(n,n), 6Li(n,t), 10B(n,αγ), 10B(n,α), C(n,n), Au(n,γ), 235U(n,f)...
none3Vitenea-J is a coupled multigroup cross section library in the standard VITAMIN-J energy group ...
A preventing shield for neutrons and gamma rays was designed using alternate layers of water and iro...
Motivated by the increased importance of high-fidelity modeling capabilities that can improve the ec...
In fusion reactors, neutron induced radioactivity strongly depends on the irradiated material. So, a...
Experimental measurements of the differential cross sections for the production of gamma rays in nat...
The gamma-rays produced by the inelastic scattering of 14 MeV neutrons. in fusion reactor materials ...
Experimental results are discussed for: /sup 6/ /sup 7/Li(n,/sup 4/He) cross sections at 14 MeV, neu...
The objectives of this paper are (1) to provide background information on the US Magnetic Fusion Rea...
The 14 MeV neutron work at Lawrence Livermore National Laboratory (LLNL) covers two main areas of in...
"For the U.S. Army Chemical Corps Nuclear Defense Laboratory"--Fore."Contract no.: DA-18-108-405-CML...
The original ANSL-V cross-section libraries (ORNL-6618) were developed over a period of several year...
The multi-group cross-section generation capability for neutrons is implemented in the FRENDY nuclea...
Multigroup cross-section covariance matrices are presented for fission in /sup 235/U, /sup 238/U, /s...
A nuclear data library was created for medium-energy-neutron-transport calculations. The 60-group li...
Evaluations are being done for the H(n,n), 6Li(n,t), 10B(n,αγ), 10B(n,α), C(n,n), Au(n,γ), 235U(n,f)...
none3Vitenea-J is a coupled multigroup cross section library in the standard VITAMIN-J energy group ...
A preventing shield for neutrons and gamma rays was designed using alternate layers of water and iro...
Motivated by the increased importance of high-fidelity modeling capabilities that can improve the ec...
In fusion reactors, neutron induced radioactivity strongly depends on the irradiated material. So, a...
Experimental measurements of the differential cross sections for the production of gamma rays in nat...
The gamma-rays produced by the inelastic scattering of 14 MeV neutrons. in fusion reactor materials ...
Experimental results are discussed for: /sup 6/ /sup 7/Li(n,/sup 4/He) cross sections at 14 MeV, neu...
The objectives of this paper are (1) to provide background information on the US Magnetic Fusion Rea...
The 14 MeV neutron work at Lawrence Livermore National Laboratory (LLNL) covers two main areas of in...
"For the U.S. Army Chemical Corps Nuclear Defense Laboratory"--Fore."Contract no.: DA-18-108-405-CML...
The original ANSL-V cross-section libraries (ORNL-6618) were developed over a period of several year...
The multi-group cross-section generation capability for neutrons is implemented in the FRENDY nuclea...