A complex of computer programmes called MULGA is described which will produce multigroup cross sections in a format suitable for input into a selection of reactor codes. Always bearing in mind that the spatial variation of flux will frustrate any determination of "exact" cross sections the maximum accuracy has been striven for within the limitations of urgency and feasibility. The programmes; together with an associated microscopic data library tape, and a specialised monitor system, have been coded for an IBM 1620 computer with 4 magnetic tapes. The basic programmes MULGA 1 and MULGA 2 have already been adapted for an ISM 7090 and the whole series will be modified for the new site computer in 1964
A compilation is presented, in the twenty-five group Reactor Nuclear Data Tape format, of neutron cr...
A preventing shield for neutrons and gamma rays was designed using alternate layers of water and iro...
Neutron cross section standards are the basis for the determination of most neutron cross sections. ...
The multi-group cross-section generation capability for neutrons is implemented in the FRENDY nuclea...
For safety studies of transmutation concepts and ADS designs, the SIMMER code is under development a...
The program was written for the Philco-2000 computer to provide a nuclear design computing tool equi...
The ETOE-2/MC/sup 2/-2/SDX code system provides a comprehensive neutron cross-section processing cap...
The MORSE code is a multipurpose neutron and gamma-ray transport Monte Carlo code. Through the use o...
Neutron Cross Sections presents the principles of cross-section measurement and use, as well as suff...
The IAEA is presently engaged in a project which is designed to use a step-by-step approach to verif...
Results of studies aimed at the further refinement of the ROCOCO system (routine for calculation and...
The FOEHN critical experiment was analyzed to validate the use of multigroup cross sections and Oak ...
In this article we examine the procedures to determine total cross sections from neutron transmissio...
An effort is now underway to produce a new evaluation of the neutron standards. It is important to m...
Reactor physics codes rely on cross-section data to determine, for example, flux profiles or burn-up...
A compilation is presented, in the twenty-five group Reactor Nuclear Data Tape format, of neutron cr...
A preventing shield for neutrons and gamma rays was designed using alternate layers of water and iro...
Neutron cross section standards are the basis for the determination of most neutron cross sections. ...
The multi-group cross-section generation capability for neutrons is implemented in the FRENDY nuclea...
For safety studies of transmutation concepts and ADS designs, the SIMMER code is under development a...
The program was written for the Philco-2000 computer to provide a nuclear design computing tool equi...
The ETOE-2/MC/sup 2/-2/SDX code system provides a comprehensive neutron cross-section processing cap...
The MORSE code is a multipurpose neutron and gamma-ray transport Monte Carlo code. Through the use o...
Neutron Cross Sections presents the principles of cross-section measurement and use, as well as suff...
The IAEA is presently engaged in a project which is designed to use a step-by-step approach to verif...
Results of studies aimed at the further refinement of the ROCOCO system (routine for calculation and...
The FOEHN critical experiment was analyzed to validate the use of multigroup cross sections and Oak ...
In this article we examine the procedures to determine total cross sections from neutron transmissio...
An effort is now underway to produce a new evaluation of the neutron standards. It is important to m...
Reactor physics codes rely on cross-section data to determine, for example, flux profiles or burn-up...
A compilation is presented, in the twenty-five group Reactor Nuclear Data Tape format, of neutron cr...
A preventing shield for neutrons and gamma rays was designed using alternate layers of water and iro...
Neutron cross section standards are the basis for the determination of most neutron cross sections. ...