The JENDL Dosimetry File based on Japanese Evaluated Nuclear Data Library Version 3 (JENDL-3) was compiled, and integral tests of the dosimetry cross section data were performed by the Dosimetry Integral Test Working Group of the Japanese Nuclear Data Committee. Sixty-one reaction cross sections and their covariance data are stored in the JENDL Dosimetry File. The cross sections were mainly taken from JENDL-3 and the covariances from IRDF-85. The data are given in the neutron energy region below 20 MeV in point and group files in the ENDF/B-V format. In order to confirm reliability of data in the JENDL Dosimetry File, several integral tests were carried out: comparison with average cross sections measured in fission neutron and fast reactor spectra, DT, and Li(d,n) neutron fields. As a result, it has been found that the calculated and the measured average cross sections are in general agreement with each other. However, some of the dosimetry cross sections still showed marked discrepancies between the measured and the calculated data. These discrepant cross sections have been reevaluated and the integral tests have been repeated.

Background: Medication errors associated with anticancer agents may cause fatal events. Therefore, exact verification of the prescription order and accurate preparation of the mixture of anticancer injections are required for safe management in cancer chemotherapy. Methods: A computer-assisted biohazard safety cabinet was newly developed for verification and preparation of anticancer agents. Using a barcode reader, information on prescription orders was transmitted from an electronic medical record to the computer system installed in the safety cabinet. The computer was controlled using a 3-button foot switch, which avoided interruption of the mixing procedure. A monitor on the cabinet wall displayed the required amounts of anticancer injections and any special information for the dissolution or mixing procedure. The names of anticancer agents were verified using a personal digital assistant and the volume of injection taken, which was automatically converted to weight on the basis of the specific gravity of anticancer solution, was recorded on the computer through a digital scale. Results: Accuracy and efficiency in mixing anticancer injections were compared between procedures with and without the present apparatus. Errors in the amounts were much smaller and the time spent in preparation was significantly shorter using the present apparatus. Conclusions: The present computer-assisted biohazard safety cabinet for preparation of the mixture of anticancer agents is considered to be potentially useful for the safe management in cancer chemotherapy.

The JENDL Dosimetry File, which contains 67 dosimetry reactions, has been revised by the Dosimetry Integral Test Working Group of the Japanese Nuclear Data Committee. Thirty-one cross sections and their covariance data were simultaneously evaluated mainly through a generalized least-squares code using the experimental data in EXFOR. In order to confirm the reliability of the present revised data, integral tests have been carried out by comparing the calculated spectrum-averaged cross sections with the measured ones in fission neutron fields, fast/thermal reactor neutron fields, D-T and D-Li fusion-like neutron fields. In most of the dosimetry cross sections, it has been found that the ratios of calculated to experimental results on their integral tests show reasonable agreement within predicted uncertainty, while unreasonable discrepancies are still observed in some revised JENDL dosimetry cross sections.

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Monte Carlo seminars have been held at Japan Atomic Energy Institute. There are 1) Monte Carlo fundamental theory, 2) sub-criticality seminar with Monte Carlo method for nuclear fuel cycle facilities, 3) shielding safety analysis seminar with Monte Carlo method, 4) estimation method of lower weight bound for neutron deep penetration problem with Monte Carlo method, 5) shielding safety analysis at high energy with MCNPX code, 6) streaming safety analysis seminar with Monte Carlo method, 7) skyshine analysis seminar with Monte Carlo method, 8) dosimetry seminar with Monte Carlo method. In the fundamental theory seminar, new estimation method for lower weight bound or importance are introduced. In the sub-criticality seminar, eleven benchmark experiment problems conducted by the authors are introduced in order to confirm the reliability of calculation method.KEYWORDS: Monte Carlo seminars, fundamental theory, sub-criticality, shielding analysis, estimation method of lower weight bound, neutron deep penetration problem, shielding analysis at high energy, streaming, skyshine, dosimetry, new estimation method for lower weight bound, eleven benchmark experiment problems