SCDAP/RELAP5 independent peer review

The SCDAP/RELAP5 code has been developed for best-estimate transient simulation of light-water-reactor coolant systems during severe accidents. The newest version of the code is SCDAP/RELAP5/MOD3. The US Nuclear Regulatory Commission (NRC) decided that there was a need for a broad technical review of the code by recognized experts to determine overall technical adequacy, even though the code is still under development. For this purpose, an eight-member SCDAP/RELAP5 Peer Review Committee was organized, and the outcome of the review should help the NRC prioritize future code-development activity. Because the code is designed to be mechanistic, the Committee used a higher standard for technical adequacy than was employed in the peer review of the parametric MELCOR code. The Committee completed its review of the SCDAP/RELAP5 code, and the findings are documented in this report. Based on these findings, recommendations in five areas are provided: (1) phenomenological models, (2) code-design objectives, (3) code-targeted applications, (4) other findings, and (5) additional recommendations

User`s Guide for the KBERT 1.0 Code: For the Knowledge-Based Estimation of Hazards of Radioactive Material Releases From DOE Nuclear Facilities

The possibility of worker exposure to radioactive materials during accidents at nuclear facilities is a principal concern of the DOE. The KBERT software has been developed at Sandia National Laboratories under DOE support to address this issue by assisting in the estimation of risks posed by accidents at chemical and nuclear facilities. KBERT is an acronym for Knowledge-Based system for Estimating hazards of Radioactive material release Transients. The current prototype version of KBERT focuses on calculation of doses and consequences to in-facility workers due to accidental releases of radioactivity. This report gives detailed instructions on how a user who is familiar with the design, layout and potential hazards of a facility can use KBERT to assess the risks to workers in that facility. KBERT is a tool that allows a user to simulate possible accidents and observe the predicted consequences. Potential applications of KBERT include the evaluation of the efficacy of evacuation practices, worker shielding, personal protection equipment and the containment of hazardous materials

User's guide for the KBERT 2.0 code

The possibility of worker exposure to radioactive materials during accidents at nuclear facilities is a principal concern of the DOE. The KBERT analysis tool has been developed at Sandia National Laboratories under DOE support to address this issue by assisting in the estimation of risks posed by accidents at chemical and nuclear facilities. KBERT is an acronym for Knowledge-Based system for Estimating hazards of Radioactive material release Transients. KBERT's primary purpose is to predict doses to in-facility workers due to accidental releases of radioactivity. Models are also in KBERT for predicting doses to the public based upon plume dispersal models. This report gives detailed instructions on how a user, starting with knowledge of design, layout and potential hazards of a facility, can use KBERT to assess the risks to workers in that facility and to the public as a result of releases from the facility. A key feature of KBERT is the inclusion of the non-facility-specific material release, radioactive decay, and dose databases (i.e., knowledge bases) that might also be needed for such an assessment. The material release characteristics are based on the 1994 DOE Handbook for airborne release fractions/rates and respirable fractions for nonreactor nuclear facilities. Another important feature of KBERTis the inclusion of a transparent interface between KBERTand the Nuclear Regulatory Commission's CONTAIN code. This interface enables KBERT to use the validated and proven flow models in CONTAIN to predict inter-room airflows. Potential applications of KBERT include the evaluation of the consequences of evacuation practices, the effect of personal protection equipment, and the degree of containment of hazardous materials

Examination on Philosophy-Based Management of Contemporary Japanese Corporations: Philosophy, Value Orientation and Performance

corporate management philosophy, corporate value orientation, corporate performance,

Bullying in the U.S. Workplace: Normative and Process-Oriented Ethical Approaches

A-B-C-model, human resource management, legal, moral principles, workplace bullying,