核科技图书馆科技报告征订

一、反应堆和核电厂

 

H-093-001

法国创新钠冷快堆的得失平衡氧化物燃料堆芯：中子研究结果

A break even oxide fuel core for an innovative French sodium-cooled fast reactor: neutronic studies results. [B,e]//global 2009, 2009, p.1521-1529 [001]

 

H-093-002

增加电生产效率的快堆组件设计变更

Fast reactor subassembly design modifications for increasing electricity generation efficiency. [B,e] //global 2009, 2009, p.1537-1547[001]

 

H-093-003

轻水堆到快增殖堆过渡期快增殖堆堆芯概念研究

Study on FBR core concepts for the LWR-to-FBR transition period. [B,e]// global 2009, 2009, p.1548-1556[001]

 

H-093-004

钠冷大尺寸快堆混合氧化物燃料堆芯参数最佳化

Optimization of parameters of MOX fuel core of sodium cooled large size fast reactor. [B,e]//global 2009, 2009, p.1557-1564[001]

 

H-093-005

采用钍燃料的液态金属冷却堆的中子评估

Neutronic assessment of liquid-metal cooled fast reactors using thorium fuel. [B,e]//global 2009, 2009, p.1602-1610 [001]

 

H-093-006

凤凰堆运行的35年：为未来系统获得的科学知识和运行反馈

35 years of Phenix operation: acquired scientific knowledge and operating feedback for the system of the future. [B,e]//global 2009, 2009, p.1646-1650 [001]

 

H-093-007

实验增殖堆2号的运行和试验经验

Operating and test experience for the experimental breeder reactor II (EBR- II). [B,e]//global 2009, 2009, p.1651- 1659[001]

 

H-093-008

用氟-20标记剂监测钠冷快堆功率

Sodium fast reactor power monitoring using 20F tagging agent. [B,e]//global 2009, 2009, p.1660-1668[001]

 

H-093-009

用铅-铋共晶体自然循环冷却的低功率快堆

A low power fast reactor cooled by natural circulation of LBE. [B,e]// global 2009, 2009, p.1669-1673[001]

H-093-010

在钠回路中采用主堆辅助冷却系统或直接反应堆辅助冷却系统的衰变热排除的编码确认

Code validation for decay heat removal using PRACS or DRACS in a sodium loop. [B,e]//global 2009, 2009, p.1674-1681 [001]

 

H-093-011

不同燃料轻水冷却堆和重水冷却堆的增殖和反应性空穴的比较分析

Comparative analysis on breeding and void reactivity of light and heavy water -cooled reactor for different fuels. [B,e]//global 2009, 2009, p.1682-1689 [001]

 

H-093-012

用两流体模型分析编码ACE-3D数值模拟超临界水冷堆燃料组件的热工-水力特性

Numerical simulation on thermal- hydraulic characteristics in fuel assemblies of supercritical water cooled reactors using two-fluid model analysis code ACE-3D. [B,e]//global 2009, 2009, p.1690-1693[001]

 

H-093-013

超临界水冷堆燃料和堆芯设计研究

SCWR (Super-critical water cooled reactor) fuel and core design study. [B,e]//global 2009, 2009, p.1694-1702 [001]

 

H-093-014

为再循环钚或超铀元素的灵活燃料循环的先进轻水堆概念的早期采用堆芯的设计

Early introduction core design for advanced LWR concept of FLWR to recycle Pu or TRU.[B,e]//global 2009, 2009, p.1703-1710[001]

 

H-093-015

钍-铀233压水堆增殖堆热设计可行性

Thermal design feasibility of Th-U233 PWR breeder. [B,e]//global 2009, 2009, p.1711-1721[001]

 

H-093-016

以高温气冷堆为基础的区域动力工业的创新技术

Innovation technology for regional power industry based on HTGR. [B,e]// global 2009, 2009, p.1722-1729[001]

 

H-093-017

用蒙特-卡罗堆芯贫化计算进行超高温堆堆芯衰变热分析

Decay heat analysis of a VHTR core by Monte Carlo core depletion calculation. [B,e]//global 2009, 2009, p.1730-1736 [001]

 

H-093-018

高性能轻水堆的再热器设计概念

Reheater design concept for the high performance light water reactor. [B,e] //global 2009, 2009, p.1737-1744[001]

 

H-093-019

高性能轻水堆电站控制

Plant control of the high performance light water reactor. [B,e]//global 2009, 2009, p.1745-1756[001]

 

H-093-020

模块卵石床先进高温堆的发展进展

Progress in the development of the modular pebble-bed advanced high temperature reactor. [B,e]//global 2009, 2009, p.1757-1764[001]

 

H-093-021

次锕系元素嬗变用反应堆燃烧堆效率的比较研究

Comparative study of the reactor burner efficiency for transmutation of minor actinides. [B,e]//global 2009, 2009, p.1843-1846[001]

 

H-093-022

坎杜堆用于次锕系元素嬗变的显著潜力

Outstanding potential of CANDU reactors for the transmutation of minor actinides. [B,e]//global 2009, 2009, p.1847-1856 [001]

 

H-093-023

用单束断路和电流方式运行的裂变室对次临界堆进行第一次反应性测定

First reactivity determination of a subcritical reactor using a single beam- trip and fission chambers operating in current mode. [B,e]//global 2009, 2009, p.1801-1808[001]

 

H-093-024

熔盐堆利用能力和燃烧效率的最佳化

Optimization of the burning efficiency and of the deplogment capacities of the molten salt reactor. [B,e]//global 2009, 2009, p.1864-1872[001]

 

H-093-025

轻水堆和重水堆中的镅嬗变

Transmutation of americium in light and heavy water reactors. [B,e]//global 2009, 2009, p.1873-1885[001]

 

H-093-026

在快增殖堆再循环系统中增加长寿命裂变产物嬗变率的新靶概念

New target concepts for increase in transmutation rate of LLFP in FBR recycle system. [B,e]//global 2009, 2009, p.1906-1913[001]

 

H-093-027

在先进大功率钠冷快堆中利用次锕系元素的可能性

Possibilities of minor actinides utilization in advanced large power sodium cooled fast reactor. [B,e]// global 2009, 2009, p.1914-1921 [001]

 

H-093-028

中等尺寸钠冷快堆中镅浓度的上限

Upper limits to americium concentration in medium size sodium cooled fast reactors. [B,e]//global 2009, 2009, p.1935-1943[001]

 

H-093-029

作为次锕系元素嬗变器的钠冷快堆的性能研究计算

Exploratory calculations of sodium fast reactor performances as a minor actinide transmuter. [B,e]//global 2009, 2009, p.1944-1948[001]

 

H-093-030

钠冷快堆二氧化铀再生区和二氧化铀与二氧化钚燃料中非均匀次锕系元素嬗变：堆芯性能评估

Heterogeneous minor actinide transmutation on a UO2 blanket and on (U, Pu)O2 fuel in a sodium-cooled fast reactor-Assessment of core performances. [B,e]//global 2009, 2009, p.1949-1956 [001]

 

H-093-031

钠冷快堆：空穴系数和废物最小化：用MURE编码进行中子物理学研究

Sodium-cooled fast reactors: void coefficient and waste minimization: neutronics studies using MURE. [B,e]// global 2009, 2009, p.1957-1966[001]

 

H-093-032

先进水冷堆局部中子耦合流动所致不稳定性机械模拟能力的发展

Development of mechanistic modeling capabilities for local neutronically- coupled flow-induced instabilities in advanced water-cooled reactors.[R,e]// DOE/ID-14707, 2009, 22p.[001]

 

H-093-033

IRP-R1 TRIGA核反应堆的实验热工-水力分析

Experimental thermal-hydraulic analysis of the IPR-R1 TRIGA nuclear reactor.[R,e]//INIS-BR-6462, 2006, 11p. [001]

 

H-093-034

IPR-R1 TRIGA核反应堆偏离泡核沸腾的实验预测

Experimental prediction of departure from nucleate boiling on the IPR-R1 TRIGA nuclear reactor.[R,e]//INIS-BR- 6464, 2006, 9p.[001]

 

H-093-035

用起源运算法则对普通与微散热片管内对流沸腾进行传热系数关联

Heat transfer coefficient correlation for convective boiling inside plain and micro fin tubes using genetic algorithms. [R,e]//INIS-BR-6466, 2006, 9p.[001]

 

H-093-036

水平圆形管道中分层气液两相流的模拟

Modeling of stratified gas-liquid two- phase flow in horizontal circular pipes. [R,e]//INIS-BR-6468, 2006, 10p.[001]

 

H-093-037

水冷堆先进燃料芯块材料和燃料棒设计技术会议（文摘）

Technical meeting on advanced fuel pellet materials and fuel rod designs for water cooled reactors. Book of abstracts.[R,e]//INIS-XA-1074, 2009, 23p.[001]

 

H-093-038

在役检查中裂纹探测概念假设对风险减少的影响研究

Studies on the effect of flaw detection probability assumptions on risk reduction at inspection.[R,e]//NKS-208, 2009, 71p.[001]

 

H-093-039

瑞典林哈尔压水堆的裂变气体排放数据

Fission gas release data for Ringhals PWR.[R,e]//SKB-TR-09-26, 2009, 15p. [001]

 

H-093-040

核反应堆严重事故现象学的SARNET讲稿

SARNET lecture notes on nuclear reactor severe accident phenomenology.[R,e]// CEA-R-6194, 2008, 425p.[001]

 

H-093-041

衰变动力的全面实验确认

Decay power: a comprehensive experimental validation.[R,e]//CEA-R- 6213, 2009, 194p.[001]

 

H-093-042

Creole实验的新评价：用JEFF3.1.1核数据库确定压水堆反应性温度系数

A new evaluation of the Creole experiment. Qualification of the PWR reactivity temperature coefficient using JEFF3.1.1 nuclear data library. [R,e]//CEA-R-6215, 2009, 139p.[001]

 

H-093-043

第4代气冷堆的整体模型：在超高温堆中的应用

A global model for gas cooled reactors for the generation-4: application to the very high temperature reactor (VHTR). [R,f]//FRNC-TH-7694, 2006, 176p.[001]

 

H-093-044

三里岛事故和法国核电站安全的经验教训

The three mile island accident and its learning for the safety of nuclear power plants in France.[R,f]//INIS-FR-10- 0164, 2009, 18p.[001]

 

H-093-045

关于可持续发展要求创新快堆概念可能性评估

Assessment of the potential of innovative fast reactor (FR) concepts in relation to the requirements of sustainable development.[R,f]//IPNO-T- 08-09, 2008, 186p.[001]

 

H-093-046

第4代反应堆：综合注释

Fourth generation type reactors- Synthesis. note[R,f]//IRSN-2007-41-FR, 2007, 55p.[001]

 

H-093-047

发电用压水堆的严重事故

Serious accidents of PWR type reactors for power generation.[R,f]//IRSN-2008- 98-FR, 2008, 53p.[001]

 

H-093-048

为改进超铀元素焚烧研究磁约束聚变的重要进展

Exploitation of a breakthrough in magnetic confinement fusion to improve transuranic incineration. [B,e]// global 2009, 2009, p.1833-1842[001]

 

H-093-049

第4届IAEA关于等离子体不稳定性理论技术会议文摘

Abstracts of 4. IAEA technical meeting on the theory of plasma instabilities. [R,e]//INIS-XA-09N1817, 2009, vp.[001]

 

二、核燃料和核材料

 

H-093-050

嬗变系统用铅、铅-铋共晶体技术和材料研究

Lead, lead-bismuth eutectic technologies and materials studies for transmutation systems. [B,e]//global 2009, 2009, p.1773-1781[001]

 

H-093-051

Obrigheim压水堆中钍-钚混合氧化物的辐照（燃耗达37.7百万千瓦日/吨）

Irradiation of thorium-plutonium mixed oxide fuel to 37.7GWd/tonne in the Obriyheim pressurized water reactor (KWO). [B,e]// global 2009, 2009, p. 1857-1863[001]

 

H-093-052

超铀元素用作超高温堆系统燃料成分：尾段考虑

Utilization of transuranics as fuel component in VHTR systems: the back-end considerations. [B,e]// global 2009, 2009, p.1886-1893[001]

 

H-093-053

具有次锕系元素燃料的先进再循环堆

Advanced recycling reactor with minor actinide fuel. [B,e]// global 2009, 2009, p.1922-1930[001]

 

H-093-054

利用惰性基体燃料来嬗变锕系元素的比较：低转换快燃烧堆中的混合氧化物和再循环

A comparison of actinide transmutation using inert matrix fuels. MOX and recycle in a low conversion fast burner reactor. [B,e]// global 2009, 2009, p.1931-1934[001]

 

H-093-055

钠冷快堆金属燃料发展情况

Status of metallic fuel development for sodium-cooled fast reactor. [B,e]// global 2009, 2009, p.1974-1979[001]

 

H-093-056

含次锕系元素的快堆金属燃料的辐照后检验：燃耗约为2.5（原子百分率）燃料的裂变气体释放和金相学

Post-irradiation examinations on fast reactor metal fuels containing minor actinides-Fission gas release and metallography of ～2.5 at. % burnup fuels. [B,e]// global 2009, 2009, p.1980-1989 [001]

 

H-093-057

快堆铀-钚-锆燃料中组成重新分布模拟进展

Advances in modeling of constituent redistribution in fast reactor U-Pu-Zr fuel. [B,e]// global 2009, 2009, p.1990- 1996[001]

 

H-093-058

含超铀元素的金属燃料的发展情况

Status of transuranic bearing metallic fuel development. [B,e]// global 2009, 2009, p.1997-2005[001]

 

H-093-059

快中子辐照对打算作为含次锕系元素的嬗变靶支撑基体的惰性材料的热物理性质的影响

Fast neutron irradiation impact on thermophysical properties of inert materials intended as support matrix for transmutation targets bearing minor actinides. [B,e]// global 2009, 2009, p.2016-2022[001]

 

H-093-060

次锕系元素再分布迁移模型的发展和确认

Development and verification of a migration model for minor actinide redistribution. [B,e]// global 2009, 2009, p.2036-2044[001]

 

H-093-061

高含量镅混合氧化物（Am-MOX）燃料次锕系元素再循环概念评价及其制造过程发展

Evaluation of MA recycling concept with high Am-containing MOX (Am-MOX) fuel and development of its fuel fabrication process. [B,e]// global 2009, 2009, p.2045-2050[001]

 

H-093-062

快堆混合氧化物燃料芯块先进制造工艺流程发展

Development of an advanced fabrication process for fast reactor MOX fuel pellets. [B,e]// global 2009, 2009, p. 2051-2058[001]

 

H-093-063

用常规粉末冶金工艺流程制造含次锕系元素材料及其表征

Fabrication and characterization of minor actinides bearing materials by conventional powder metallurgy process. [B,e]// global 2009, 2009, p.2059-2064 [001]

 

H-093-064

用离子交换树脂制备次锕系元素靶或再生区

Preparation of minor actinides targets or blankets by the mean of ionic exchange resin. [B,e]// global 2009, 2009, p. 2065-2067[001]

 

H-093-065

铀氧化物和含镧系元素铀氧化物烧结时的特征

Characterization of uranium oxide and Ln -bearing uranium oxide during sintering. [B,e]// global 2009, 2009, p.2068[001]

 

H-093-066

以纳米束反冲为基础的嬗变结构

Nano-clustered recoil based transmutation structure. [B,e]// global 2009, 2009, p.2077-2086[001]

 

H-093-067

快堆中长寿命裂变产物嬗变靶制造研究

Study on target fabrication for LLFR transmutation by fast reactors. [B,e]// global 2009, 2009, p.2087-2094[001]

 

H-093-068

钠冷快堆中二氧化铀再生区和二氧化铀与二氧化钚燃料中的非均匀次锕系元素嬗变：细棒和组件初步设计

Heterogeneous minor actinide transmutation on UO2 blanket and on    ( U,Pu) O2 fuel in a sodium fast reactor- Preliminary design of pin and subassembly. [B,e]// global 2009, 2009, p.2095-2103[001]

 

H-093-069

ECRIX-H实验：最初辐照后检验和模拟

ECRIX-H experiment: first post- irradiation examinations and simulations. [B,e]// global 2009, 2009, p.2104-2115[001]

 

H-093-070

闭式燃料循环次锕系元素燃烧策略

Strategy of minor actinide burning for closed fuel cycle. [B,e]// global 2009, 2009, p.1894-1905[001]

 

H-093-071

镅钚混合氧化物/惰性基体系统的结构研究

Structural investigation on americium and plutonium mixed oxides/inert matrices systems. [B,e]// global 2009, 2009, p.2023-2029[001]

H-093-072

惰性基体燃料工作的进展

The advancement of work on inert matrix fuel. [B,e]// global 2009, 2009, p.2035 [001]

 

H-093-073

快堆燃料类型和反应堆安全性能

Fast reactor fuel type and reactor safety performance. [B,e]// global 2009, 2009, p.1530-1536[001]

 

H-093-074

长寿命小快堆不同驱动燃料和钚生产的比较分析

Comparative analysis on different driver fuel and plutonium production of long-life small fast reactor. [B,e]// global 2009, 2009, p.1565-1574[001]

 

H-093-075

快堆SVBR-100的燃料循环

Fuel cycle of reactor SVBR-100. [B,e]// global 2009, 2009, p.1575-1583[001]

 

H-093-076

无化学后处理快堆中最大燃料利用

Maximum fuel utilization in fast reactors without chemical reprocessing. [B,e]// global 2009, 2009, p.1584-1591 [001]

 

H-093-077

在先进试验堆中进行下一代核电站/先进气冷堆燃料辐照实验

The next generation nuclear plant/ advanced gas reactor fuel irradiation experiments in the advanced test reactor. [B,e]// global 2009, 2009, p.1765-1772 [001]

 

H-093-078

采用碳化物燃料改进钠冷快堆堆芯的研究

A search for improved SFR cores using carbide fuel. [B,e]// global 2009, 2009, p.1621-1630[001]

 

H-093-079

巴西-阿根廷核材料衡算与控制机构2003年报

Annual report ABACC 2003-Brazilian- Argentine Agency for the Accounting and Control of Nuclear Materials. [R,e]// INIS-BR-6420, 2003, 67p.[001]

 

H-093-080

用碳酸铀酰铵共沉淀和机械混合工艺流程晶种法得到的二氧化铀-10%（重量）三氧化二钆燃料芯块研究

Study of UO2-10WT% Gd2O3 fuel pellets obtained by seeding method using AUC co- precipitation and mechanical mixing processes.[R,e]// INIS-BR-6424, 2008, 19p.[001]

 

H-093-081

具有雅可比椭圆形横截面形状的核燃料棒的热性能

Thermal performance of nuclear fuel rod with a Jacobian elliptic cross sectional form.[R,e]// INIS-BR-6459, 2006, 12p. [001]

 

H-093-082

高驱动铝基二元合金的无定形和纳米结晶相的形成

Amorphous and nanocrgstalline phase formation in highly-driven AL-based binary alloys.[R,e]//IS-T-2684, 225p. [001]

 

H-093-083

二氧化铀-三氧化二钆核燃料生产程序的技术问题

Technological aspects concerning the production procedures of UO2-Gd2O3 nuclear fuel.[R,e]// INIS-BR-6469, 2007, 6p.[001]

H-093-084

核燃料高燃耗结构形成的了解

A contribution on the understanding of the high burn-up structure formation in nuclear fuels.[R,e]//FRNC-TH-7626, 2007, 209p.[001]

 

三、安全、事故、辐射防护、测量和环境

 

H-093-085

辐照钍燃料操作的辐射安全评估

Assessment of radiological safety for irradiated thorium fuel handling operations.[R,e]//INIS-AR-E-013, 2008, 14p.[001]

 

H-093-086

后处理铀样品中铀-232和钍-228放射性水平的初步研究

Preliminary studies on the 232U and 228Th radioactivity levels in reprocessed uranium samples.[R,e]//INIS-AR-E-017, 2008, 6p.[001]

 

H-093-087

放射性监督用气流正比计数器的广泛应用

Comprehensive applications of the gas flow proportional counters for radiological surveillance.[R,e]// INIS -AR-E- 018, 2008, 6p.[001]

 

H-093-088

阿海珐有关部门剂量限制的执行：最佳化工具

Dose constraint implementation in AREVA group: an optimization tool.[R,e]//INIS -AR-E-019, 2008, 8p.[001]

 

H-093-089

软件COMODORE  V2007：公众由废气与废液排放接受的剂量的评估

COMODORE V2007: assessment doses for the public from atmospheric and liquid discharges.[R,e]// INIS-AR-E-020, 2008, 6p.[001]

 

H-093-090

溶液中临界性偏移所致照射的模拟

Modeling the exposure by a criticality excursion in solution.[R,e]//INIS-AR- E-025, 2008, 7p.[001]

 

H-093-091

快堆燃料后处理设施辐射防护的运行经验

Operational experiences in radiation protection in fast reactor fuel reprocessing facility.[R,e]//INIS-AR- E-027, 2008, 9p.[001]

 

H-093-092

铀矿开采和铀矿石加工地区生物物质中镭- 226运行前监测计划

Preoperational monitoring program of Ra-226 in biological material in uranium mining and milling areas. [R,e]//INIS- AR-E-028, 2008, 4p. [001]

 

H-093-093

Vandellos I核电站拆卸时的辐射防护

Radiological protection during the dismantling of Vandellos I nuclear power plant.[R,e]//INIS-AR-E-032, 2008, 9p. [001]

 

H-093-094

马库尔去污和退役工作时的辐射防护

Radiation protection during decontamination and decommissioning operations at Marcoule.[R,e]//INIS-AR- E-034, 2008, 7p.[001]

 

H-093-095

铀剩余物地区的放射性评估

Radiological assessment of an area with uranium residual material.[R,e]// INIS-AR-E-035, 2008, 7p.[001]

 

H-093-096

DR2堆退役时的辐射防护措施

Radiation protection measures during the decommissioning of DR2.[R,e]//INIS- AR-E-038, 2008, 10p.[001]

 

H-093-097

铀、钍设施的退役：辐射防护方案

Decommissioning an uranium and thorium facility: a radiation protection approach.[R,e]// INIS-AR-E-039, 2008, 6p.[001]

 

H-093-098

铀矿恢复的长期放射性影响

Long term radiological impact of a uranium mine restoration.[R,e]// INIS- AR-E-040, 2008, 8p.[001]

 

H-093-099

测定大面积陆地放射性的最佳方法：现场γ能谱测量或取样后实验室测量

Optimum method to determine radioactivity in large tracts of land. In-situ gamma spectroscopy or sampling followed by laboratory measurement.[R,e] //INIS-AR-E-041, 2008, 12p.[001]

 

H-093-100

测定200升金属桶中γ放射性的最佳方法：整体测量或取样后实验室测量

Optimum method to determine gamma activity in 200 liter drums, In-toto measurement or extracting a sample.[R,e] //INIS-AR-E-042, 2008, 10p.[001]

 

H-093-101

巴西核能研究所-国家核能委员会二氧化铀芯块制造厂为退役进行去活化的辐射防护

Radioprotection planned operation to deactivate an old fabrication plant of UO2 pellets in IPEN-CNEN/SP to perform decommissioning.[R,e]//INIS-AR-E-043, 2008, 7p.[001]

 

H-093-102

巴西米纳斯吉拉斯州Antas河流域正退役的核设施排出的废气、废液的放射性生态学影响

Radioecological impact of effluents from a nuclear facility being decommissioned in the Antas river hydrographic basin in the state of Minas Gerais, Brazil.[R,e]// INIS-AR-E-044, 2008, 6p.[001]

 

H-093-103

俄罗斯西北部乏燃料和放射性废物贮存场址放射性生态条件评估和补救标准

Radioecological condition assessment and remediation criteria for the sites of spent fuel and radioactive waste storage in the Russian northwest.[R,e] // INIS-AR-E-048, 2008, 8p.[001]

 

H-093-104

研究堆设施退役的辐射防护计划

Radiation protection planning for decommissioning of research reactor facilities.[R,e]// INIS-AR-E-049, 2008, 8p.[001]

 

H-093-105

国际核安保专题讨论会（详细摘要）

International symposium on nuclear security. Book of extended synopses. [R,e]//IAEA-CN-166, 2009, 141p.[001]

 

H-093-106

英国罗赛斯海军船坞多余核设施退役的辐射防护和放射性废物管理问题

Radiological protection and radioactive waste management aspects of the decommissioning of redundant nuclear facilities at the Rosyth Dockyard, UK. [R,e]//INIS-AR-E-051, 2008, 10p.[001]

H-093-107

（退役）操作类型的一般方法和准备：（法国）Bugey 1核电站情况

General methodology and preparation of operation type: the case of Bugey 1.[R,e] //INIS-AR-E-052, 2008, 41p.[001]

 

H-093-108

核装置退役的现场排放

Site release in the decommissioning of nuclear installations.[R,e]// INIS-AR- E-053, 2008, 6p.[001]

 

H-093-109

用蒙特-卡罗法和二氧化锆与聚四氟乙烯剂量仪进行乳房X线照相术的吸收剂量测量

Absorbed dose measurements in mammography using Monte Carlo method and ZrO2+PTFE dosemeters.[R,e]//INIS-MX- 2577, 2009, 11p.[001]

 

H-093-110

国际核燃料循环中铀原料专题讨论会：勘探、采矿、生产、供求、经济学和环境问题论文摘要补遗

Addendum to the book of abstracts for the international symposium on uranium raw material for the nuclear fuel cycle: exploration, mining, production, supply and demand, economics and environmental issues (URAM-2009).[R,e]// IAEA-CN-175 (add.), 2009, 18p.[001]

 

H-093-111

（能源）技术和国际气候政策

Technology and international climate policy.[R,e]//ETP-Discussion-Paper-2008-21, 2009, 32p.[001]

 

H-093-112

用于核保障的无损检验技术的性能评价：欧洲核保障研究发展协会无损检验工作组2002年评价

Performance values for non destructive assay (NDA) techniques applied to safeguards: the 2002 evaluation by the ESARDA NDA working group.[R,e]//INIS-BR -6419, 2003, 45p.[001]

 

H-093-113

氡：采矿环境第1次研究结果和知识的综合

The radon, synthesis of knowledge and results of first investigation in mining environment.[R,f]//INERIS-DRS-08-86108-07270A, 2008, 51p.[001]

 

H-093-114

环境放射性监督

Surveillance of the environmental radioactivity.[R,f]//INIS-FR-10-0165, 2008, 443p.[001]

 

H-093-115

铀矿尾料贮存现场影响评价方法

Method of impact evaluation of storage sites for uranium ore tailings.[R,f]// IPSN-DPRE-SERGD-01-53, 2001, 69p.[001]

 

H-093-116

核领域的安全文化

Safety culture in the nuclear field.[R,f] //IRSN-2005-54, 2005, 26p.[001]

 

H-093-117

环境辐射防护：综合和前景

Environment radiation protection- Synthesis and perspectives.[R,f]// IRSN -2005-56, 2006, 126p.[001]

 

H-093-118

辐射防护和核安全研究所对联合国原子辐射效应科学委员会报告的综合（2003-2007年）

Synthesis by IRSN of UNSCEAR reports- period 2003-2007.[R,f]//IRSN-2006-74, 2006, 41p.[001]

 

H-093-119

地下设施中氡体积活性测量方法指南

Measurement of radon voluminal activity in underground facilities. Methodological guide. [R,f]//IRSN-DEI- SARG-2006-023, 2006, 13p.[001]