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JAEA Reports

Data of long term hydro-pressure monitoring on Tono Regional Hydrogeological Study Project for fiscal year 2009

Karino, Tomoyuki; Keya, Hiromichi*; Takeuchi, Ryuji

JAEA-Data/Code 2011-001, 37 Pages, 2011/06

JAEA-Data-Code-2011-001.pdf:3.57MB

Tono Regional Hydrogeological Study (RHS) Project is a one of the geoscientific research programme at Tono Geoscience Center (TGC). This project started since April, 1992 and main investigations were finished to March 2004. Since 2005, hydrogeological and hydrochemical monitoring are continued by the existing monitoring system. This paper describes the results of the long term hydro-pressure monitoring from April, 2009 to March, 2010.

JAEA Reports

Data of long term hydro-pressure monitoring on Mizunami Underground Research Laboratory Project for fiscal year 2009

Karino, Tomoyuki; Keya, Hiromichi*; Takeuchi, Ryuji

JAEA-Data/Code 2011-002, 62 Pages, 2011/06

JAEA-Data-Code-2011-002.pdf:4.74MB

Mizunami Underground Research Laboratory (MIU) Project has three overlapping phases: Surface-based investigation phase (Phase I), Construction phase (Phase II), and Operation phase (Phase III), with a total duration of 20 years. The main goals of the MIU Project from Phase I through to Phase III are: to establish techniques for investigation, analysis and assessment of the deep geological environment, and to develop a range of engineering for deep underground application. Currently, the project is being carried out under the Phase II. One of the Phase II goals is set to develop and revise models of the geological environment using the investigation results obtained during excavation, and determine and assess the changes in the geological environment in response to excavation. The long term hydro-pressure monitoring has been continued to achieve the Phase II goals. This paper describes the results of the long term hydro-pressure monitoring from April, 2009 to March, 2010.

JAEA Reports

Hydrochemical investigation at the Mizunami Underground Research Laboratory; Compilation of groundwater chemistry in the Mizunami group and Toki granite (fiscal year 2008)

Sai, Masataka*; Shingu, Shinya; Hagiwara, Hiroki; Mizuno, Takashi

JAEA-Data/Code 2011-003, 41 Pages, 2011/06

JAEA-Data-Code-2011-003.pdf:2.18MB

This report compiles data set of the groundwater chemistry obtained at Mizunami Underground Research Laboratory (MIU) in the fiscal year 2008. These data include groundwater chemistry of inflow in the shafts and sampled groundwater in the boreholes, which drilled from sub-stages of MIU and from surface (MSB-2, MSB-4, and MIZ-1). Basic information (e.g. sampling location, sampling date, sampling method, analytical method) is also described in terms of ensuring traceability of data.

JAEA Reports

Hydrochemical investigation at the Mizunami Underground Research Laboratory; Compilation of groundwater chemistry in the Mizunami group and Toki granite (fiscal year 2009)

Shingu, Shinya; Sai, Masataka*; Hagiwara, Hiroki; Mizuno, Takashi

JAEA-Data/Code 2011-004, 49 Pages, 2011/06

JAEA-Data-Code-2011-004.pdf:2.87MB

This report compiles data set of the groundwater chemistry obtained at Mizunami Underground Research Laboratory (MIU) in the fiscal year 2009. These data include groundwater chemistry of inflow in the shafts and sampled groundwater in the boreholes, which drilled from sub-stages of MIU and from surface (MSB-2, MSB-4, and MIZ-1). Basic information (e.g. sampling location, sampling date, sampling method, analytical method) is also described in terms of ensuring traceability of data.

JAEA Reports

Development of FEP database for geological and climatic disruptive events; Uplift, subsidence, earthquake activity, and climate change (Contract research)

Sakai, Ryutaro; Takeda, Seiji; Kimura, Hideo; Matsuba, Hisashi*

JAEA-Data/Code 2011-005, 107 Pages, 2011/06

JAEA-Data-Code-2011-005.pdf:2.74MB

In the safety assessment for a geological disposal of radioactive waste such as high-level radioactive waste, it is necessary to estimate the hydrological environmental changes affected by external factors such as long-termed earthquake activity and volcanic activity. Therefore it is important to perform the informations including a wide range of future processes and conditions of engineered barriers and geosphere in a systematic manner and to construct scenarios considering external factors. Generation of geological and climatic disruptive events such as earthquake activity, volcanic activity, uplift, subsidence, climatic change and sea-level change and propagation process of their impacts and their types are needed to be clarified in order to understand the phenomena of their influence on a disposal system in case of our country. Japan Atomic Energy Agency started to develop FEP database including the correlation of FEPs and FEP data sheet.

JAEA Reports

Annual data compilation of the water balance observation in the regional hydrogeological study project (RHS Project); For the fiscal year 2008

Takeda, Masaki; Sato, Atsuya*; Takeuchi, Ryuji

JAEA-Data/Code 2011-006, 21 Pages, 2012/02

JAEA-Data-Code-2011-006.pdf:2.98MB
JAEA-Data-Code-2011-006-appendix(CD-ROM).zip:22.23MB

At the Tono Geoscientific Research Unit, the subsurface water balance observation has been carried out in order to estimate groundwater recharge rate for setting the upper boundary conditions on groundwater flow simulation and to obtain data for the calibration of the hydrogeological model. In the water balance observations, precipitation metrological data for the estimation of river flow rate, and groundwater table have been observed in the Garaishi river area and the Hiyoshi river area. The missed data and data error in the monitoring data from the fiscal year 2008 were complemented or corrected the data was compiled in data set. Both of the observation data and compiled data are included in the data set, and the data set is recorded on DVD-ROM.

JAEA Reports

Annual data compilation of the water balance observation in the Mizunami Underground Research Laboratory Project (MIU Project); From the fiscal year 2008

Takeda, Masaki; Sato, Atsuya*; Takeuchi, Ryuji

JAEA-Data/Code 2011-007, 38 Pages, 2012/02

JAEA-Data-Code-2011-007.pdf:3.15MB
JAEA-Data-Code-2011-007-appendix(CD-ROM)-1.zip:79.71MB
JAEA-Data-Code-2011-007-appendix(CD-ROM)-2.zip:67.65MB

At the Tono Geoscientific Research Unit, the subsurface water balance observation has been carried out in order to estimate groundwater recharge rate for setting the upper boundary conditions on groundwater flow simulation and to obtain data for the calibration of the hydrogeological model. In the water balance observations, precipitation metrological data for the estimation of evapotranspiration, river flow rate, and groundwater table and soil moisture have been observed in the Sheba river area, the Sheba river model area and MIU Construction Site. After missed data and data error in the monitoring data from the fiscal year 2008 were complemented or corrected, the data was compiled in data set. Both of the observation data and compiled data are included in the data set, and the data set is recorded on DVD-ROM.

JAEA Reports

Development of GSA-GCL code version 2 to evaluate radioactivity concentration limit for low level radioactive waste disposal (Contract research)

Takeda, Seiji; Sawaguchi, Takuma; Sasaki, Toshihisa*; Kimura, Hideo

JAEA-Data/Code 2011-008, 166 Pages, 2011/08

JAEA-Data-Code-2011-008.pdf:3.33MB

The upper bound of radioactivity concentration during disposal means the maximum concentration of radionuclides of waste repository allowable in a license application for that repository. For transuranium (TRU) and uranium wastes, it is necessary to amend the law to set the upper bound of radioactivity concentration for three concepts to dispose of low-level waste categories: near surface disposal without an artificial barrier (trench disposal), near surface disposal with an artificial barrier (concrete vault disposal), and intermediate depth disposal. We developed an assessment code (GSA-GCL ver.2) to derive the upper bound of radioactivity concentration for TRU and uranium wastes, according to geological and artificial barrier features in three disposal concepts. This document summaries descriptions of the capabilities and structure of GSA-GCL ver.2 code, mathematical models, user information for execution of the code system (users' manual), input and output file system and the result of verification for the models in this code. We provide the evaluated result of the upper bounds of radioactivity concentration for radionuclides in TRU wastes, which reflects to the regulation report on the result for three concepts to dispose of low-level waste categories, reviewed by Nuclear Safety Commission of Japan in May 2007.

JAEA Reports

Petrological and mineralogical data collected from the Mizunami Underground Research Laboratory construction site; Bulk chemical composition, mineral occurrence and mineral composition

Yuguchi, Takashi; Tsuruta, Tadahiko; Mizuno, Takashi; Kunimaru, Takanori

JAEA-Data/Code 2011-009, 85 Pages, 2011/09

JAEA-Data-Code-2011-009.pdf:8.93MB

Tono Geoscientific Research Unit of Japan Atomic Energy Agency (JAEA) is carrying out the Underground Research Laboratory Project, which is a scientific study revealing the deep geological environment as a basis of research and development for geological disposal of high level radioactive wastes. The aim of the project is to establish comprehensive techniques for the investigation, analysis and assessment of the deep geological environment in fractured crystalline rock, and to develop a range of engineering techniques for deep underground application. This project has three overlapping phases: Surface-based investigation phase (Phase I), Construction phase (Phase II), and Operation phase (Phase III), with a total duration of about 20 years. Nowadays, the project is under the Phase II. Phase I and II conducted the following kinds of analyses for rock samples, which was collected from the Mizunami Underground Research Laboratory construction site. (1) Bulk chemical composition analyses (major and minor elements), (2) X-ray diffraction analyses, and (3) Mineral composition analyses. Petrological and mineralogical data is a basic information for the planning of mass transfer study in Phase III investigation. Thus, this paper compiled the results of these analyses. Thus, this paper compiled the results of these analyses.

JAEA Reports

Production of neutron cross section library based on JENDL-4.0 to continuous-energy Monte Carlo code MVP and its application to criticality analysis of benchmark problems in the ICSBEP handbook

Okumura, Keisuke; Nagaya, Yasunobu

JAEA-Data/Code 2011-010, 82 Pages, 2011/09

JAEA-Data-Code-2011-010.pdf:6.25MB

In May 2010, JENDL-4.0 was released from JAEA as the updated Japanese Nuclear Data Library. It was processed by the nuclear data processing system LICEM and an arbitrary-temperature neutron cross section library MVPlib_nJ40 was produced for the neutron and photon transport calculation code MVP based on the continuous-energy Monte Carlo method. The library contains cross sections for 406 nuclides on the free gas model, thermal scattering cross sections, and cross sections of pseudo fission products for burn-up calculations with MVP. Criticality benchmark calculation was carried out with MVP and the produced library for about 1,000 cases of critical experiments stored in the ICSBEP handbook, which covers a wide variety of fuel materials, fuel forms, and neutron spectra. We report all comparison results of effective neutron multiplication factors between calculations and experiments to give a validation data for the prediction accuracy of JENDL-4.0 for criticalities.

JAEA Reports

Analysis of the radioactivity concentrations in low-level radioactive waste generated from JPDR facilities

Hoshi, Akiko; Tsuji, Tomoyuki; Tanaka, Kiwamu; Yasuda, Mari; Watanabe, Koichi; Sakai, Akihiro; Kameo, Yutaka; Kogure, Hiroto; Higuchi, Hidekazu; Takahashi, Kuniaki

JAEA-Data/Code 2011-011, 31 Pages, 2011/10

JAEA-Data-Code-2011-011.pdf:1.7MB

Simple and rapid methods to evaluate the radioactivity concentrations are required to be established for the near surface disposal of radioactive wastes generated from research facilities at Japan Atomic Energy Agency. In order to establish the methods to evaluate the radioactivity concentrations of miscellaneous solid wastes generated from research and testing reactors, we collected and analyzed samples from miscellaneous solid wastes generated by the decommissioning of JPDR (Japan Power Demonstration Reactor). In the present paper, we summarized data (262 data) about the radioactivity concentrations of the 7 important nuclides ($$^{3}$$H, $$^{14}$$C, $$^{60}$$Co, $$^{59}$$Ni, $$^{63}$$Ni, $$^{90}$$Sr, $$^{137}$$Cs) which accumulated by the analysis.

JAEA Reports

Log of refining and conversion facility dismantling; Progress in 2010FY

Editorial Committee of Refining and Conversion Facility Decommissioning Results

JAEA-Data/Code 2011-012, 216 Pages, 2011/10

JAEA-Data-Code-2011-012.pdf:4.22MB

The Refining and Conversion Facility located in the Ningyo-toge Environmental Engineering Center had the natural uranium conversion process and reprocessed uranium conversion process. The construction of this facility was started in 1979 and completed in October 1981. Dismantling of equipments in radiation controlled area of this facility was started from 2008. Equipments in radiation controlled area (excluding ventilating equipment and liquid waste treatment equipment) will be dismantled by the 2011 fiscal year, and ventilating equipment and liquid waste treatment equipment will be dismantled by the 2014 fiscal year. This report is a record of the dismantlement situation of the Refining and Conversion Facility in 2010 fiscal years. Concretely, dismantlement logs, dismantlement material, and secondary waste are published.

JAEA Reports

Construction of average adult Japanese voxel phantoms for dose assessment

Sato, Kaoru; Takahashi, Fumiaki; Satoh, Daiki; Endo, Akira

JAEA-Data/Code 2011-013, 87 Pages, 2011/12

JAEA-Data-Code-2011-013.pdf:8.12MB

ICRP adopted the adult reference phantoms based on the Caucasian data. In future, the dosimetric quantities calculated using these phantoms will be used for the radiation protection. However, there are some cases that the anatomical characteristics influence the organ doses. Therefore, it is needed to consider the anatomical characteristics of the subjects. Since the body sizes and organ masses of adult Japanese are smaller than those of adult Caucasian, the authors constructed the averaged adult male and female phantoms by modifying the previously developed JM and JF Japanese phantoms. In modification processes, (1) the body sizes were agreed with the Japanese averages; (2) the organ masses were adjusted to the Japanese averages within 10%, and (3) the organs, which were newly added for evaluation of the effective dose in ICRP Publ.103, were modeled. This report describes the construction, and anatomical and dosimetric characteristics of the newly constructed Japanese phantoms.

JAEA Reports

Development of the point kinetics solver, Pointkinetics in the next generation reactor analysis code system, MARBLE

Fukaya, Yuji

JAEA-Data/Code 2011-014, 55 Pages, 2011/12

JAEA-Data-Code-2011-014.pdf:3.86MB

The next generation reactor analysis code system, MARBLE version 1.0 had been developed to solve the static neutronic characteristics of reactors including burnup calculation. To solve transient problem in the MARBLE, neutronic kinetics module should be implemented. The neutronic kinetics composes space kinetics and point kinetics. Therefore, the objective of this development is to implement the point kinetics. First, theoretical categorization of the methods to solve kinetic problem was performed. Second, implementation and evaluation of the error for these methods was performed. As a result, it is found that the method using matrix exponential is preferable to apply for the point kinetics calculation due to the high reliability. Furthermore, the calculation time is not significant now. However, the knowledge obtained by the theoretical categorization or the error evaluation profits for the future development of space kinetics in the MARBLE.

JAEA Reports

Development of the single channel thermal hydraulic code, HARP for FBRs in the next generation reactor analysis code system, MARBLE

Fukaya, Yuji

JAEA-Data/Code 2011-015, 99 Pages, 2011/12

JAEA-Data-Code-2011-015.pdf:5.79MB

The conceptual studies for the Next Generation Simulation Code (NGSC) to simulate various fields of phenomena had been performed. As a result, the development of a next generation reactor analysis code system, MARBLE version 1.0, was developed. At this stage, the ability of the MARBLE version 1.0 is only to estimate the nuclear characteristics of FBRs. However, the plan of the NGSC includes LWR analysis and coupling calculations to connect various fields of estimation. In this context, the HARP has been developed as a thermal hydraulic module in the part of the MARBLE. With this module, the temperature, which is essential to estimate power coefficient of reactivity, can be estimated only by the MARBLE system. It is expected to profit for the evolution of the MARBLE as the platform for coupling calculations, because the HARP is the first thermal hydraulic solver of the MARBLE.

JAEA Reports

Code-B-1 for stress/strain calculation for TRISO fuel particle (Contract research)

Aihara, Jun; Ueta, Shohei; Shibata, Taiju; Sawa, Kazuhiro

JAEA-Data/Code 2011-016, 10 Pages, 2011/12

JAEA-Data-Code-2011-016.pdf:2.11MB

We have developed Code-B-1 for the prediction of the failure probabilities of the coated fuel particles for the high temperature gas-cooled reactors (HTGRs) under operation by modification of an existing code. A finite element method (FEM) is employed for the stress calculation part and Code-B-1 can treat the plastic deformation of the coating layer of the coated fuel particles which the existing code cannot treat.

JAEA Reports

Preparation of fast reactor group constant sets UFLIB.J40 and JFS-3-J4.0 based on the JENDL-4.0 data

Sugino, Kazuteru; Jin, Tomoyuki*; Hazama, Taira; Numata, Kazuyuki*

JAEA-Data/Code 2011-017, 44 Pages, 2012/01

JAEA-Data-Code-2011-017.pdf:2.23MB

Fast reactor group constant sets UFLIB.J40 and JFS-3-J4.0 were prepared, which are based on the latest Japanese evaluated nuclear data library JENDL-4.0. Concerning UFLIB.J40, several fine group constant sets, which covered 70-group, 73-group, 175-group and 900-group structures, and the ultra fine group constant set were prepared. The number of nuclides for cross-sections of lumped fission products was extended so as to follow the extension of the number of fissile species for fission yield data.

JAEA Reports

Development of neutron transport calculation codes for 3-D hexagonal geometry; Development of NSHEX, MINIHEX and MINISTRI codes

Sugino, Kazuteru

JAEA-Data/Code 2011-018, 125 Pages, 2012/01

JAEA-Data-Code-2011-018.pdf:4.04MB

Transport calculation codes for 3D hexagonal geometry have been developed: nodal code NSHEX, hexagonal-mesh finite difference code MINIHEX, and triangle-mesh finite difference code MINISTRI, which can perform neutron transport calculations with high accuracy for fast reactor cores. NSHEX is improved by extending the polynomial expansion order of intranode fluxes for better accuracy. MINIHEX is modified in the process of negative flux fix-up. In addition, MINISTRI is newly produced by changing the basic algorithm of MINIHEX. NSHEX, MINIHEX, and MINISTRI are applied to various fast reactor cores. It is found that these codes show satisfactory performance in terms of calculation accuracy. However, reduction of calculation time and improvement of convergence performance are required for all the codes by such measure as introduction of suitable acceleration technique. Further, development of post process functions is desired, which is represented by perturbation calculation scheme.

JAEA Reports

SIERRA-II; Simulation system (II) for emergency dose by released radioactive substances

Takeyasu, Masanori; Takeishi, Minoru*

JAEA-Data/Code 2011-019, 23 Pages, 2012/02

JAEA-Data-Code-2011-019.pdf:2.95MB

A computer code system (SIERRA-II) has been developed to estimate the environmental radiological impact of accidental releases of radionuclides from a nuclear facility in real time. The SIERRA-II is based on a three-dimensional mass-conserving wind field model and a particle dispersion model with a nesting function to calculate with high spatial resolution in the vicinity of the facility. Input includes on-line local meteorological and effluent data observed and monitored at the site of the facility, and local meteorological data as predicted by an atmospheric dynamic model. The SIERRA-II was validated using environmental monitoring data for ambient dose rate as observed at monitoring posts around the Tokai Reprocessing Plant when Kr-85 was discharged during its operation. The observed increase of the dose rate was simulated well. The agreement of calculated and observed dose rate was within a factor of 5 for 74 % of observations.

JAEA Reports

Nuclide inventories of spent fuels from light water reactors

Okumura, Keisuke; Okamoto, Tsutomu

JAEA-Data/Code 2011-020, 193 Pages, 2012/02

JAEA-Data-Code-2011-020.pdf:33.53MB

Accurate information on nuclide inventories of spent fuels from Light Water Reactors (LWRs) is important for evaluations of criticality, decay heat, radioactivity, toxicity, and so on, in the safety assessments of storage, transportation, reprocessing and waste disposal of the spent fuels. So, a lot of lattice burn-up calculations were carried out for the possible fuel specifications and irradiation conditions in Japanese commercial LWRs by using the latest nuclear data library JENDL-4.0 and a sophisticated lattice burn-up calculation code MOSRA-SRAC. As a result, burn-up changes of nuclide inventories and their possible ranges were clarified for 21 heavy nuclides and 118 fission products, which are important from the viewpoint of impacts to nuclear characteristics and nuclear fuel cycle and environment.

JAEA Reports

Subcritical dimensions for design study of future reprocessing facility

Suto, Toshiyuki; Fukushima, Manabu*

JAEA-Data/Code 2011-021, 91 Pages, 2012/02

JAEA-Data-Code-2011-021.pdf:3.57MB

Future reprocessing facilities are considered to treat not only LWR uranium fuels but also LWR-MOX fuels and even FBR fuels. These spent fuels have various enrichments, isotopic compositions of plutonium. In order to make reasonable design and management of criticality safety for such multi-fuel reprocessing facilities, there needs to be critiricality safety data with a multiple of enrichments, isotopic compositions of plutonium. The authors calculated subcritical dimensions of uranium/plutonium mixed nitrate solution with a multiple set of enrichments and isotopic compositions of plutonium for cylinder, slab, and annular geometries and arranged the results in tables and graphs which are usable for the criticality safe design study of future reprocessing facilities. In addition, some findings useful for selecting criticality safety control methods were summarized.

JAEA Reports

Development of Sorption Database (JAEA-SDB); Update of sorption data including soil and cement systems

Suyama, Tadahiro; Tachi, Yukio

JAEA-Data/Code 2011-022, 34 Pages, 2012/03

JAEA-Data-Code-2011-022.pdf:1.99MB

The present report focuses on updating of the sorption database (JAEA-SDB) by adding Kd data for various systems including soil and cement systems, to apply JAEA-SDB for the PA-related Kd setting for disposal of low level radioactive wastes including TRU wastes and the evaluation of radionuclide transport in surface soil systems. The updated data includes Kd data for soil and cement systems extracted from mainly previous published database, and Kd data related to our recent activities on the Kd setting and mechanistic model development. As a result, 16,000 Kd data from 334 references are added, total Kd values in the JAEA-SDB are about 46,000. The updated JAEA-SDB is expected to make it possible to obtain quick overview of the available data, and to have suitable access to the respective data for the performance assessment of various types of radioactive waste.

JAEA Reports

Data of groundwater from boreholes, river water and precipitation for the Horonobe Underground Research Laboratory Project; 2001-2010

Amano, Yuki; Yamamoto, Yoichi; Nanjo, Isao; Murakami, Hiroaki; Yokota, Hideharu; Yamazaki, Masanori; Kunimaru, Takanori; Oyama, Takahiro*; Iwatsuki, Teruki

JAEA-Data/Code 2011-023, 312 Pages, 2012/02

JAEA-Data-Code-2011-023.pdf:5.46MB
JAEA-Data-Code-2011-023(errata).pdf:0.08MB

In the Horonobe Underground Research Laboratory (URL) Project, ground water from boreholes, river water and precipitation have been analyzed for the environmental monitoring since the fiscal year 2001. This report shows the data set of water chemistry since the fiscal year 2001 to the fiscal year 2010.

JAEA Reports

Development of the environmental data management system

Tatebe, Kazuaki; Suzuki, Yurina; Shirato, Seiichi; Sato, Yoshinori

JAEA-Data/Code 2011-024, 84 Pages, 2012/02

JAEA-Data-Code-2011-024.pdf:2.87MB

The recent society requires business activities with environmental consideration to every enterprise. Also, Japanese laws require those activities. For example, "Environmental Consideration Law" mandates publication of a report relating to the activities of environmental consideration to each enterprise over a certain size. "Act on the Rational Use of Energy" mandates the report of the results of energy consumption and the long-term plan of the rational use of energy. Moreover, "Act on Promotion of Global Warming Countermeasures" mandates the report of the greenhouse gas emissions. In addition to those, "Water Pollution Control Law" and other environmental laws as well as environmental ordinances require business activities with environmental consideration to all companies. So, it is very important for JAEA to report business activities with environmental consideration in order to build up trustful relations with the people and communities. The Environmental Data Management System has been developed as the data base of business activities with environmental consideration at JAEA and the means to promote the activities at every site and office of JAEA. This report summarizes the structure of the environmental data management system, kinds of environmental performance data treated by the system, and gathering methods of the data.

JAEA Reports

JENDL FP decay data file 2011 and fission yields data file 2011

Katakura, Junichi

JAEA-Data/Code 2011-025, 73 Pages, 2012/03

JAEA-Data-Code-2011-025.pdf:2.59MB

The decay and fission yield data of fission products were compiled as JENDL FP decay data file 2011 (JENDL/FPD-2011) and JENDL FP fission yields data file 2011 (JENDL/FPY-2011). After the release of the JENDL FP decay data file 2000 file which was released in 2000, new measured data have been accumulated and new TAGS (Total Absorption $$gamma$$-ray Spectroscopy) data have been published. The JENDL/FPD-2011 file was then compiled to reflect the new measured data. In order to keep the consistency between the number of the nuclides contained, fission yields file, JENDL/FPY-2011 was also compiled. The decay heat calculations for various kinds of fissioning nuclides were performed to confirm the validity of the JENDL/FPD-2011 and JENDL/FPY-2011 files. The calculated results showed good agreement with the measured data. The uncertainty analyses of the decay heat calculation were carried out with the method of sensitivity analysis.

JAEA Reports

Revised version of SSCAT; Simplified shielding calculation system for high energy proton accelerator facilities

Oguri, Tomomi*; Masukawa, Fumihiro; Nakane, Yoshihiro; Nakashima, Hiroshi

JAEA-Data/Code 2011-026, 25 Pages, 2012/03

JAEA-Data-Code-2011-026.pdf:2.07MB

The simplified shielding calculation (SSCAT) system is a calculation system for radiation shielding design of high energy proton accelerator facilities, based on Moyer's and Tesch's formulae for bulk shielding and Stapleton's formula for neutron skyshine. SSCAT was originally developed for conceptual shielding design calculations of the J-PARC (Japan Proton Accelerator Research Complex) facilities, and was recently revised in order to cope with safety analysis for the licensing of the J-PARC facilities and shielding design for other proton accelerator facility. This report describes the recent status of SSCAT.

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